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Investigation of uncertainty caused by random arrangement of coated fuel particles in HTTR criticality calculations

Ho, H. Q.; 本多 友貴; 後藤 実; 高田 昌二

Annals of Nuclear Energy, 112, p.42 - 47, 2018/02

Coated fuel particle (CFP) is one of important factors attributing to the inherent safety feature of high temperature engineering test reactor (HTTR). However, the random arrangement of CFPs makes the simulation more complicated, becoming one of the factors affects the accuracy of the HTTR criticality calculations. In this study, an explicit random model for CFPs arrangement, namely realized random packing (RRP), was developed for the whole core of HTTR using a Monte-Carlo MCNP6 code. The effect of random placement of CFPs was investigated by making a comparison between the RRP and conventional uniform models. The results showed that the RRP model gave a lower excess reactivity than that of the uniform model, and the more number of fuel columns loading into the core, the greater the difference in excess reactivity between the RRP and uniform models. For example, the difference in excess reactivity increased from 0.07 to 0.17%$$Delta$$k/k when the number of fuel column increased from 9 to 30. Regarding the control rods position prediction, the RRP showed the results, which were closer to experiment than the uniform model. In addition, the difference in control rods position between the RRP and uniform models also increases from 12 to 17 mm as increasing number of fuel columns from 19 to 30.


Pair distribution function analysis of nanostructural deformation of calcium silicate hydrate under compressive stress

Bae, S.*; Jee, H.*; 兼松 学*; 城 鮎美*; 町田 晃彦*; 綿貫 徹*; 菖蒲 敬久; 鈴木 裕士

Journal of the American Ceramic Society, 101(1), p.408 - 418, 2018/01


ケイ酸カルシウム水和物(CSH)に関する原子レベルの構造や変形機構には不明な点が多い。本研究では、X線散乱法に基づく原子対相関関数(PDF)により、ケイ酸三カルシウム(C$$_{3}$$S)ペースト中に存在するCSH相のナノ構造変形挙動を評価した。単軸圧縮負荷を受けるC$$_{3}$$Sペーストの変形を、ひずみゲージ,ブラッグピークシフト, PDFから求められるマクロからミクロな変形より評価した。PDF解析により、0-20${AA}$の範囲ではCSH相の影響が支配的であること、その一方で、20${AA}$を超える範囲では、他の結晶相の影響が支配的であることが明らかとなった。CSHの変形に支配的である20${AA}$以下の範囲では、塑性変形を示すステージI(0-10MPa)と、弾性変形を示すステージIIの2つの変形過程に分けられることが分かった。その一方で、20${AA}$以上の範囲では、水酸化カルシウムに似た変形を示した。10MPa以下では、層間水やゲル水の移動に伴い、CSHの高密度化を生じたと考えられるが、除荷後には、その移動した水がCSH中に戻ることにより、変形が回復している可能性がある。


Development of an altitude-keeping system for underwater robots using laser beams

武村 史朗*; 田場 凌*; 平山 慶太*; Tansuriyavong, S.*; 川端 邦明; 相良 慎一*; 小笠原 敬*

Artificial Life and Robotics, 22(4), p.405 - 411, 2017/12



Application of topographical source model for air dose rates conversions in aerial radiation monitoring

石崎 梓; 眞田 幸尚; 石田 睦司; 宗像 雅広

Journal of Environmental Radioactivity, 180, p.82 - 89, 2017/12




A Power spectrum approach to tally convergence in Monte Carlo criticality calculation

植木 太郎

Journal of Nuclear Science and Technology, 54(12), p.1310 - 1320, 2017/12




Broad linewidth of antiferromagnetic spin wave due to electron correlation

森 道康

Journal of the Physical Society of Japan, 86(12), p.124705_1 - 124705_7, 2017/12

We study magnetic excitations in a bilayer of antiferromagnetic (AF) insulator and correlated metal, in which the double occupancy is forbidden. Effective action of AF spinwave in the AF insulator is derived by using the path integral formula within the second order of an inter-plane coupling. The electrons correlation in the metallic plane is treated by the Gutzwiller approximation, which renormalizes the hopping integrals as proportional to hole density. Remarkable is that the AF magnons are broaden at low energies, only when the metallic planes includes correlation effect. The present results will be useful also to another bilayer of metal and ferrimagnet.


Effect of alloying elements on grain boundary sliding in magnesium binary alloys; Experimental and numerical studies

染川 英俊*; 都留 智仁

Materials Science and Engineering A, 708, p.267 - 273, 2017/12




Benchmarking of economic evaluation models for an advanced loop-type sodium cooled fast reactor

向井田 恭子; 加藤 篤志; 塩谷 洋樹; 早船 浩樹; 小野 清

Nuclear Engineering and Design, 324, p.35 - 44, 2017/12



Effect of topsoil removal and selective countermeasures on radiocesium accumulation in rice plants in Fukushima paddy field

Yang, B.*; 恩田 裕一*; 大森 良弘*; 関本 均*; 藤原 徹*; 脇山 義史*; 吉村 和也; 高橋 純子*; Sun, X.*

Science of the Total Environment, 603-604, p.49 - 56, 2017/12


In this study, the effect of topsoil removal measure and fertilizer application on radiocesium uptake by rice plants was investigated over a four-year period. The results indicate that the effect of topsoil removal measure on the accumulation of radiocesium in rice plants was effective. We summarized four year's data to further confirm that potassium and nitrogen fertilizers had an opposite effect on the accumulation of radiocesium in rice plants. Increasing potassium and reducing nitrogen fertilizer conditions tended to inhibit the radiocesium uptake by rice plants.


RELAP5 uncertainty evaluation using ROSA/LSTF test data on PWR 17% cold leg intermediate-break LOCA with single-failure ECCS

竹田 武司; 大津 巌

Annals of Nuclear Energy, 109, p.9 - 21, 2017/11


An experiment was conducted for the OECD/NEA ROSA-2 Project using LSTF, which simulated a cold leg intermediate-break loss-of-coolant accident with 17% break in a PWR. Assumptions were made such as single-failure of high-pressure and low-pressure injection systems. In the LSTF test, core dryout took place because of rapid drop in the core liquid level. Liquid was accumulated in upper plenum, SG U-tube upflow-side and inlet plena because of counter-current flow limiting (CCFL). The post-test analysis by RELAP5/MOD3.3 code revealed that peak cladding temperature (PCT) was overpredicted because of underprediction of the core liquid level due to inadequate prediction of accumulator flow rate. We found the combination of multiple uncertain parameters including the Wallis CCFL correlation at the upper core plate, core decay power, and steam convective heat transfer coefficient in the core within the defined uncertain ranges largely affected the PCT.


Benchmark experiment on copper with graphite by using DT neutrons at JAEA/FNS

権 セロム*; 太田 雅之*; 佐藤 聡*; 今野 力; 落合 謙太郎*

Fusion Engineering and Design, 124, p.1161 - 1164, 2017/11





芳中 一行

技術士, 29(11), p.12 - 15, 2017/11





羽賀 勝洋

波紋, 27(4), p.155 - 158, 2017/11



Estimation of $$Delta$$${it R}$/${it R}$ values by benchmark study of the M$"o$ssbauer Isomer shifts for Ru, Os complexes using relativistic DFT calculations

金子 政志; 安原 大樹*; 宮下 直*; 中島 覚*

Hyperfine Interactions, 238(1), p.36_1 - 36_9, 2017/11

Ru, Os錯体の結合状態に対する密度汎関数計算の妥当性を評価することを目的として、$$^{99}$$Ru, $$^{189}$$Osのメスバウアー異性体シフト実験値を用いて理論計算手法のベンチマークを行った。結果、Ru錯体およびOs錯体の原子核位置での電子密度の計算値はメスバウアー異性体シフト実験値とよく相関した。


New precise measurement of muonium hyperfine structure interval at J-PARC

上野 恭裕*; 青木 正治*; 深尾 祥紀*; 東 芳隆*; 樋口 嵩*; 飯沼 裕美*; 池戸 豊*; 石田 啓一*; 伊藤 孝; 岩崎 雅彦*; et al.

Hyperfine Interactions, 238(1), p.14_1 - 14_6, 2017/11


MuSEUM is an international collaboration aiming at a new precise measurement of the muonium hyperfine structure at J-PARC (Japan Proton Accelerator Research Complex). Utilizing its intense pulsed muon beam, we expect a ten-fold improvement for both measurements at high magnetic field and zero magnetic field. We have developed a sophisticated monitoring system, including a beam profile monitor to measure the 3D distribution of muonium atoms to suppress the systematic uncertainty.


Inter atomic force constants of $$beta$$-PbF$$_{2}$$ from diffuse neutron scattering measurement

Xianglian*; Bao, W.*; Guo, T.*; Li, P.*; 佐久間 隆*; 井川 直樹

International Journal of Innovation in Science and Mathematics, 5(6), p.165 - 167, 2017/11

633Kにて$$beta$$-PbF$$_{2}$$の中性子散漫散乱実験を実施した結果、振動性のある散漫強度が観察された。この振動性散漫散乱は原子の熱振動に起因する相関効果によって説明することができ、この相関効果とDebye-Waller熱因子から計算して得られた、第1、第2最近接原子間の力定数は各々、0.36eV/$AA $^{2}$$ (距離; ${it r}$ = 2.599 $AA )$、0.21eV/$AA $^{2}$$ (${it r}$=3.001 $AA )$と求められた。


Thermodynamic equilibrium constants for important isosaccharinate reactions; A Review

Rai, D.*; 北村 暁

Journal of Chemical Thermodynamics, 114, p.135 - 143, 2017/11


イソサッカリン酸はセルロースの分解生成物であり、低レベル放射性廃棄物処分場で発生する。このイソサッカリン酸は、処分場に存在するアクチニド元素など多くの元素と強い錯体を作ることが知られている。われわれは、イソサッカリン酸の解離およびラクトン化定数や、Ca, Fe(III), Th, U(IV), U(VI), Np(IV), Pu(IV)およびAm(III)との錯生成定数をレビューした。また、イソサッカリン酸共存下における地層処分場でのアクチニド元素の移行挙動を予測するための錯生成定数について総括し、利用可能なデータが不十分な場合の熱力学データの信頼性を確保するための追加の研究について概説した。


Distribution of $$^{137}$$Cs on components in urban area four years after the Fukushima Dai-ichi Nuclear Power Plant accident

吉村 和也; 斎藤 公明; 藤原 健壮

Journal of Environmental Radioactivity, 178-179, p.48 - 54, 2017/11

This study evaluated relative $$^{137}$$Cs inventory on urban surfaces to the initial inventory on plane permeable field in evacuation zone about four years after the Fukushima Dai-ichi Nuclear Power Plant accident. The average relative inventory of paved ground was 0.18, accounting for 20% of that on plane permeable ground. Other urban surfaces showed small average values less than 0.1, indicating rapid removal of radiocesium from urban surfaces. Roads, roofs and rooftops, however, showed large variations in the relative inventories, which occasionally exceeded 0.4. Difference in material was indicated to be a factor of the variation observed for roofs/rooftops. Different relative inventories were found for roads and roofs between this study and the case in Europe, suggesting the importance to evaluate regionally-specific relative inventory on urban surfaces.


Role of soil-to-leaf tritium transfer in controlling leaf tritium dynamics; Comparison of experimental garden and tritium-transfer model results

太田 雅和; Kwamena, N.-O. A.*; Mihok, S.*; Korolevych, V.*

Journal of Environmental Radioactivity, 178-179, p.212 - 231, 2017/11



Experimental characterization of concrete removal by high-power quasicontinuous wave fiber laser irradiation

Nguyen, P. L.; 大道 博行; 山田 知典; 西村 昭彦; 長谷川 登*; 河内 哲哉*

Journal of Laser Applications, 29(4), p.041501_1 - 041501_11, 2017/11



Enhanced orbital magnetic moment in FeCo nanogranules observed by Barnett effect

緒方 裕大; 中堂 博之; Gu, B.; 小林 伸聖*; 小野 正雄; 針井 一哉; 松尾 衛; 齊藤 英治; 前川 禎通

Journal of Magnetism and Magnetic Materials, 442, p.329 - 331, 2017/11


The gyroscopic g factor, $$g'$$, of FeCo nanogranules embedded in a matrix of MgF$$_2$$ (FeCo-MgF$$_2$$) was determined by measuring the magnetic-field generation from a rotating sample due to the Barnett effect. The $$g'$$ value of the FeCo-MgF$$_2$$ is estimated to be 1.76 $$pm$$ 0.11. The orbital contribution to the magnetic moment in the FeCo nanogranules was found to be quite large compared with that in bulk FeCo, being consistent with a density-functional-theory calculation that shows that the orbital magnetic moment may increase at the FeCo/MgF$$_2$$ interfaces. The result suggests that the orbital magnetic moment is enhanced by symmetry breaking at the surface of the FeCo nanogranules.


Study of the neutron multiplication effect in an active neutron method

米田 政夫; 大図 章; 森 貴正; 中塚 嘉明; 前田 亮; 呉田 昌俊; 藤 暢輔

Journal of Nuclear Science and Technology, 54(11), p.1233 - 1239, 2017/11




Development of a hybrid ECT sensor for JSFR SG double-wall tubes

山口 智彦; Mihalache, O.

Journal of Nuclear Science and Technology, 54(11), p.1201 - 1214, 2017/11

A new design has been adopted for the steam generators (SG) tubes of the Japan Sodium-cooled Fast Reactor (JSFR) using double-wall tubes. This paper estimates and assesses the effectiveness of detecting defects in SG double-wall tubes of the JSFR by using combined high-frequency eddy current testing (ECT) and low-frequency remote field eddy current (RF-ECT) sensors. We confirm that the proposed hybrid ECT sensor is highly sensitive to small defects, fatigue cracks, and other defects even when located under support plates of tubes. The parameters of the hybrid ECT sensor are designed and optimized to detect small defects using accurate numerical simulations based on the finite element method (FEM), using an in-house developed code. The sensitivity and high performance of the hybrid ECT sensor was validated with experimental measurements.


Updating of local blockage frequency in the reactor core of SFR and PRA on consequent severe accident in Monju

西村 正弘; 深野 義隆; 栗坂 健一; 鳴戸 健一*

Journal of Nuclear Science and Technology, 54(11), p.1178 - 1189, 2017/11



Distributions of density and fission products in the reaction product between irradiated MOX fuel and molten zircaloy-2

石見 明洋; 勝山 幸三; 前田 宏治; 古屋 廣高*

Journal of Nuclear Science and Technology, 54(11), p.1274 - 1276, 2017/11



Development of determination method of $$^{93}$$Mo content in metal waste generated at the Japan Power Demonstration Reactor

島田 亜佐子; 大森 弘幸*; 亀尾 裕

Journal of Radioanalytical and Nuclear Chemistry, 314(2), p.1361 - 1365, 2017/11



Measurement and estimation of the $$^{99}$$Mo production yield by $$^{100}$$Mo($$n,2n$$)$$^{99}$$Mo

湊 太志; 塚田 和明*; 佐藤 望*; 渡辺 智*; 佐伯 秀也*; 川端 方子*; 橋本 慎太郎; 永井 泰樹*

Journal of the Physical Society of Japan, 86(11), p.114803_1 - 114803_6, 2017/11





天本 一平

Journal of the Society of Inorganic Materials, Japan, 24(391), p.393 - 401, 2017/11



Research and development on pyrochemical treatment of spent nitride fuels for MA transmutation in JAEA

林 博和; 佐藤 匠; 柴田 裕樹; 津幡 靖宏

NEA/NSC/R(2017)3, p.427 - 432, 2017/11



Effects of $$gamma$$ irradiation on the adsorption characteristics of xerogel microcapsules

大西 貴士; 田中 康介; 小山 真一; Ou, L. Y.*; 三村 均*

NEA/NSC/R(2017)3, p.463 - 469, 2017/11

資源の有効利用、廃棄物低減のために、無機イオン交換体(タングストリン酸アンモニウム(AMP)またはフェロシアン化銅(KCuFC))をアルギネートゲルで内包するマイクロカプセル(AWP-ALGまたはKCuFC-ALG)、および、アルギネートゲルそのもの(ALG)を用いた核種分離システムの開発を実施している。ALG, AWP-ALGおよびKCuFC-ALGは、それぞれ、Zr, CsおよびPdを選択的に吸着することが明らかになっている。しかしながら、$$gamma$$線照射に伴う吸着特性の変化については、十分に調べられていない。そこで、$$^{60}$$Co線源によって$$gamma$$線を3898kGyまで照射した後、各種マイクロカプセルの吸着特性を評価した。その結果、AWP-ALGまたはKCuFC-ALGは、内包する無機イオン交換体によってCsまたはPdを吸着するため、$$gamma$$線照射を通して吸着特性に変化は見られなかった。一方、ALGは$$gamma$$線照射に伴って放射線分解が進行し、Zrに対する吸着特性が低下した。


Hillocks created for amorphizable and non-amorphizable ceramics irradiated with swift heavy ions; TEM study

石川 法人; 田口 富嗣*; 大久保 成彰

Nanotechnology, 28(44), p.445708_1 - 445708_11, 2017/11




長寿命核種の分離変換技術の現状,4; 加速器駆動システムを用いた核変換システムと分離変換技術の成熟度

辻本 和文; 荒井 康夫; 湊 和生

日本原子力学会誌, 59(11), p.644 - 648, 2017/11



福島の環境回復に向けた取り組み,7; 福島沿岸域における放射性セシウムの動きと存在量

乙坂 重嘉; 小林 卓也; 町田 昌彦

日本原子力学会誌, 59(11), p.659 - 663, 2017/11




河野 裕子

日本原子力学会誌, 59(11), P. 671, 2017/11



第16回学術大会(大分); 一般演題-E2 放射線計測-2

三上 智

日本放射線安全管理学会誌, 16(2), P. 41, 2017/11



Creep-fatigue evaluation method for weld joints of Mod.9Cr-1Mo steel, 1; Proposal of the evaluation method based on finite element analysis and uniaxial testing

安藤 勝訓; 高屋 茂

Nuclear Engineering and Design, 323, p.463 - 473, 2017/11



Establishment of a Laboratory for $$gamma$$-ray Spectrometry of Environmental Samples Collected in Fukushima

三枝 純; 依田 朋之; 前田 智史; 岡崎 勤; 大谷 周一; 山口 敏夫; 栗田 義幸; 波澄 篤; 米澤 仲四郎*; 武石 稔

Proceedings of 14th International Congress of the International Radiation Protection Association (IRPA-14), Vol.3 (Internet), p.1078 - 1085, 2017/11

2011年3月の福島第一原子力発電所の事故後、原子力機構は新たに放射能分析施設を福島に立ち上げた。分析施設では高分解能$$gamma$$線スペクトロメトリに基づき、土壌や水、ダストフィルタ、植物といった環境試料の放射能分析を月当たり約1,000件のペースで行っている。2012年9月の施設立上げ以来、分析結果の信頼性や、分析依頼者及び機器オペレータの利便性向上を目指した技術開発を実施し、制度的・技術的な課題を継続的に改善することで、ISO/IEC 17025規格に適合する試験所としての認定を得た。


Application of a communication-avoiding generalized minimal residual method to a gyrokinetic five dimensional Eulerian code on many core platforms

井戸村 泰宏; 伊奈 拓也*; 真弓 明恵; 山田 進; 松本 和也*; 朝比 祐一*; 今村 俊幸*

Proceedings of 8th Workshop on Latest Advances in Scalable Algorithms for Large-Scale Systems (ScalA 2017), p.7_1 - 7_8, 2017/11

ジャイロ運動論的5次元オイラーコードGT5Dに省通信一般化最小残差(CA-GMRES)法を適用し、一般化共役残差(GCR)法を用いたオリジナルコードとの性能比較をJAEA ICEX(Haswell)、Plasma Simulator(FX100)、Oakforest-PACS(KNL)において実施した。CA-GMRES法はGCR法に比べて約3.8倍の演算密度となることから、メモリとネットワークの帯域が制限された将来のエクサスケールアーキテクチャに適合する。性能評価の結果、GCR法に比べて計算カーネルは1.47$$sim$$2.39倍加速され、1,280ノード処理におけるデータ縮約通信は全体コストの5$$sim$$13%から約1%に削減された。


An Application of the probabilistic fracture mechanics code PASCAL-SP to risk informed in-service inspection for piping

真野 晃宏; 山口 義仁; 勝山 仁哉; Li, Y.

Proceedings of Asian Symposium on Risk Assessment and Management 2017 (ASRAM 2017) (USB Flash Drive), 12 Pages, 2017/11

米国等では原子力発電所の配管系を対象として、リスク情報を活用した供用期間中検査(RI-ISI)が広く実施されている。Westinghouse Owners Groupが開発したRI-ISI手法では、配管系をセグメントに区分し、非破壊試験を考慮した配管セグメントの漏えい頻度に基づいて、試験程度を決定する。配管セグメントの漏えい頻度の評価には、試験における亀裂の検出確率を亀裂寸法によらず一定値とみなす等の仮定に基づく統計モデルが用いられている。一方で、確率論的破壊力学(PFM)解析では、現実に即した亀裂検出確率評価モデルにより、詳細に漏えい頻度を評価可能である。原子力機構では、経年事象や非破壊試験等を考慮して配管セグメントの漏えい頻度を評価可能なPFM解析コードPASCAL-SPを開発している。本研究では、PASCAL-SPを用いて、試験チームの熟練度、試験時期及び補修範囲の考え方について異なる条件の下でセグメントの漏えい頻度及び試験程度を評価した。その結果、試験程度を現実に即して柔軟に評価できることから、PASCAL-SPはRI-ISIにおける有効なツールであると結論付けた。


An Estimation method of flaw distributions reflecting inspection results through Bayesian update

Lu, K.; 宮本 裕平*; 真野 晃宏; 勝山 仁哉; Li, Y.

Proceedings of Asian Symposium on Risk Assessment and Management 2017 (ASRAM 2017) (USB Flash Drive), 9 Pages, 2017/11



A Refined analysis on the power reactivity loss measurement in Monju

谷中 裕; 竹越 淳; 岸本 安史*; 毛利 哲也; 宇佐美 晋

Progress in Nuclear Energy, 101(Part C), p.329 - 337, 2017/11



Identification of penetration path and deposition distribution of radionuclides in houses by experiments and numerical model

廣内 淳; 高原 省五; 飯島 正史; 渡邊 正敏; 宗像 雅広

Radiation Physics and Chemistry, 140, p.127 - 131, 2017/11

The dose assessment for people living in preparation zones for the lifting of the evacuation order is needed with the return of the residents. However, it is difficult to assess exactly indoor external dose rate because the indoor distribution and infiltration pathways of radionuclides are unclear. This paper describes indoor and outdoor dose rates measured in eight houses in the difficult-to-return zone in Fukushima prefecture to examine the distribution of radionuclides in a house and the main infiltration pathway of radionuclides. In addition, it describes also dose rates calculated with a Monte Carlo photon transport code to understand thoroughly the measurements. These measurements and calculations provide that radionuclides can infiltrate mainly through ventilations, windows, and doors, and then deposit near the gaps, while those infiltrate hardly through sockets and air conditioning outlets.


最新放射線化学(応用編),13; マイクロドジメトリの観点から見た線量の不均一性

佐藤 達彦

Radioisotopes, 66(11), p.507 - 512, 2017/11



Magnetic Bragg dip and Bragg edge in neutron transmission spectra of typical spin superstructures

間宮 広明*; 大場 洋次郎; 寺田 典樹*; 渡邉 騎通*; 廣井 孝介; 篠原 武尚; 及川 健一

Scientific Reports (Internet), 7(1), p.15516_1 - 15516_8, 2017/11



Localization of cesium on montmorillonite surface investigated by frequency modulation atomic force microscopy

荒木 優希*; 佐藤 久夫*; 奥村 雅彦; 大西 洋*

Surface Science, 665, p.32 - 36, 2017/11





土田 豊*; 海老原 健一

鉄と鋼, 103(11), p.653 - 659, 2017/11



Effect of crystal orientation on incipient plasticity during nanoindentation of magnesium

染川 英俊*; 都留 智仁; Singh, A.*; 三浦 誠司*; Schuh, C. A.*

Acta Materialia, 139, p.21 - 29, 2017/10




Inductively coupled plasma-mass spectrometry

江坂 文孝

Analytical Sciences, 33(10), p.1097 - 1098, 2017/10



Evaluation of the accuracy of mono-energetic electron and beta-emitting isotope dose-point kernels using particle and heavy ion transport code system: PHITS

椎葉 拓郎*; 久峩 尚也*; 黒岩 靖淳*; 佐藤 達彦

Applied Radiation and Isotopes, 128, p.199 - 203, 2017/10


単色電子や$$beta$$放出核種の線量・点カーネル(ある点線源による吸収線量の減衰を線源からの距離の関数として表したもの)は、RI内用療法などの治療計画で極めて重要となる。本研究では、粒子・重イオン輸送計算コードPHITSを用いて単色電子(0.015, 0.1, 1.0, 2.0MeV)及び$$beta$$放出核種($$^{89}$$Sr, $$^{90}$$Y, $$^{131}$$I)の水及び骨に対する線量・点カーネルを計算し、EGSnrc, GATE6.0, MCNP4C, FLUKAなど他の計算コードによる結果と比較した。その結果、PHITSによる計算結果は他のコードの結果と概ね4%の範囲内で一致した。この結果から、PHITSを用いて計算した線量・点カーネルはRI内用療法の線量評価に用いるのに十分な精度を有していると考えられる。


Mesoporous alumina as an effective adsorbent for molybdenum (Mo) toward Instant production of radioisotope for medical use

Saptiama, I.*; Kaneti, Y. V.*; 鈴木 裕美*; 鈴木 善貴; 土谷 邦彦; 榮 武二*; 高井 公子*; 福光 延吉*; Alothman, Z. A.*; Hossain, M. S. A.*; et al.

Bulletin of the Chemical Society of Japan, 90(10), p.1174 - 1179, 2017/10




Quantitative analysis of radiocesium retention onto birnessite and todorokite

Yu, Q.*; 大貫 敏彦*; 香西 直文; 坂本 文徳; 田中 万也; 笹木 恵子*

Chemical Geology, 470, p.141 - 151, 2017/10


本研究では、2種類のMn酸化物(トドロカイトとバーネサイト)が持つCs保持能を評価した。トドロカイトには、Csの吸着選択性がバーネサイトよりも高いサイトがあることがわかった。Cs初期濃度10$$^{-9}$$mol/Lで吸着させた後、吸着したCsを1M NaClとNH$$_{4}$$Clで脱離させたところ、約34%のCsが脱離せずにトドロカイトに残った。この値はバーネサイトに残ったCsの割合よりもずっと多かった。これらの結果は、トドロカイトが土壌中の放射性Csの固定に寄与することを強く示唆する。


An Empirical model for the corrosion of stainless steel in BWR primary coolant

内田 俊介*; 塙 悟史; 内藤 正則*; 岡田 英俊*; Lister, D. H.*

Corrosion Engineering, Science and Technology, 52(8), p.587 - 595, 2017/10




熊田 高之

電子スピンサイエンス, 15(Autumn), p.86 - 91, 2017/10




内山 雄介*; 東 晃平*; 小谷 瑳千花*; 岩崎 理樹*; 津旨 大輔*; 上平 雄基; 清水 康行*; 恩田 裕一*

土木学会論文集,B2(海岸工学)(インターネット), 73(2), p.I_685 - I_690, 2017/10




小谷 瑳千花*; 内山 雄介*; 鹿島 基彦*; 上平 雄基; 御手洗 哲司*

土木学会論文集,B2(海岸工学)(インターネット), 73(2), p.I_1315 - I_1320, 2017/10



三春町、南相馬市; 福島環境安全センター三春施設・南相馬施設の取り組み

菖蒲 信博

エネルギーレビュー, 37(10), p.21 - 22, 2017/10



楢葉町; 楢葉遠隔技術開発センターの取り組み

荒川 了紀

エネルギーレビュー, 37(10), p.17 - 18, 2017/10



Detection and correlation of tephra-derived smectite-rich shear zones by analyzing glass melt inclusions in mineral grains

石井 英一; 古澤 明*

Engineering Geology, 228, p.158 - 166, 2017/10



Simulation of saturation process in a transuranium disposal facility

高山 裕介; 飯塚 敦*; 河井 克之*

Environmental Geotechnics (Internet), 4(5), p.339 - 352, 2017/10



Lead benchmark experiment with DT neutrons at JAEA/FNS

権 セロム*; 太田 雅之*; 佐藤 聡*; 今野 力; 落合 謙太郎*

Fusion Science and Technology, 72(3), p.362 - 367, 2017/10





小松 和三*; 関 健史*; 長縄 明大*; 岡 潔*; 西村 昭彦

保全学, 16(3), p.89 - 95, 2017/10



FCC metal-like deformation behaviour of Ir$$_3$$Nb with the L1$$_2$$ structure

岡本 範彦*; 竹本 昌平*; Chen, Z. M. T.*; 山口 正剛; 乾 晴行*

International Journal of Plasticity, 97, p.145 - 158, 2017/10


The deformation behaviour of Ir$$_3$$Nb with stoichiometric and off-stoichiometric compositions has been investigated as functions of crystal orientation and deformation temperature. The critical resolved shear stress (CRSS) for (111)[$$overline{1}$$01] slip in stoichiometric Ir$$_3$$Nb exhibits a marginal temperature dependence at all temperatures with neither strong negative temperature dependence at low temperatures nor positive (anomalous) temperature dependence at high temperatures. The CRSS for (111)[$$overline{1}$$01] slip exhibits orientation dependence, neither. The [$$overline{1}$$01] dislocation dissociates into the anti-phase boundary (APB)-type scheme and is observed to be smoothly curved on the (111) slip plane at all temperatures, indicating the planar core structure. This is exactly what is known for the perfect dislocation in many pure FCC metals and is the reason for the observed FCC metal-like deformation behaviour of Ir$$_3$$Nb. The absence of yield stress anomaly in Ir$$_3$$Nb is discussed in terms of anisotropy in planar fault energies and elastic constants calculated by first principles calculations and experimentally determined in the present study.


Local structure analysis of (Na$$_{0.5}$$K$$_{0.45}$$Li$$_{0.05}$$)NbO$$_3$$ synthesized by malic acid complex solution method

米田 安宏; 高田 愛梨*; 長井 遥*; 菊池 丈幸*; 森下 正夫*; 小舟 正文*

Japanese Journal of Applied Physics, 56(10S), p.10PB07_1 - 10PB07_7, 2017/10




Using two detectors concurrently to monitor ambient dose equivalent rates in vehicle surveys of radiocesium contaminated land

武石 稔; 柴道 勝; Malins, A.; 操上 広志; 村上 晃洋*; 三枝 純; 米谷 雅之

Journal of Environmental Radioactivity, 177, p.1 - 12, 2017/10



Loss of core cooling test with one cooling line inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor

藤原 佑輔; 根本 隆弘; 栃尾 大輔; 篠原 正憲; 小野 正人; 高田 昌二

Journal of Nuclear Engineering and Radiation Science, 3(4), p.041013_1 - 041013_8, 2017/10



Saturated pool nucleate boiling on heat transfer surface with deposited sea salts

上澤 伸一郎; 小泉 安郎; 柴田 光彦; 吉田 啓之

Journal of Nuclear Engineering and Radiation Science, 3(4), p.041002_1 - 041002_13, 2017/10

The progress of the accident of Fukushima Daiichi NPS has been calculated by severe accident analysis codes, for example, MAAP, SAMPSON and so on. However, the effects of the seawater on thermal-hydraulic behavior have not been considered in these calculations, although the seawater was injected into the reactors to cool down the nuclear fuels. Saturated pool nucleate boiling heat transfer experiments with on NaCl solution, natural seawater and artificial seawater were performed to examine the effects of salts on boiling heat transfer. The experimental results indicated that boiling curves were well predicted with the Rohsenow correlation although large coalescent bubble formation was inhibited in the NaCl solution, natural seawater and artificial seawater experiments. However, calcium sulfate was deposited on the heat transfer surface in the experiments with artificial seawater. After the formation of a deposit layer, a slow surface-temperature excursion was initiated at a heat flux lower than the usual critical heat flux. We confirmed that the relationship between the salt concentrations of the artificial seawater in the bulk fluid and the vaporization rate at the surface at which the slow surface-temperature excursion initiated. This relationship suggested that if the salt concentration of the seawater exceeded 11 wt%, the deposition of calcium sulfate on the heat transfer surface occurred even if the heat flux was zero.


Corrosion behavior of ODS steels with several chromium contents in hot nitric acid solutions

丹野 敬嗣; 竹内 正行; 大塚 智史; 皆藤 威二

Journal of Nuclear Materials, 494, p.219 - 226, 2017/10


高速炉用に酸化物分散強化型(ODS)鋼燃料被覆管の開発が進められている。原子力機構では9および11Cr-ODS焼戻しマルテンサイト鋼をその候補材料としている。被覆管からの腐食生成物が再処理工程に及ぼす影響を見積もるためには、その腐食挙動を評価しておく必要がある。本研究では95$$^{circ}$$Cの硝酸溶液中で基礎的な浸漬試験および電気化学試験を系統的に実施した。腐食速度は有効Cr濃度(Cr$$_{rm eff}$$)および硝酸濃度の増加に対して、指数関数的に低下した。酸化性イオンの添加も腐食速度を低下させた。取得した分極曲線や浸漬後の表面観察結果より、低Cr$$_{rm eff}$$と希硝酸の組み合わせでは浸漬初期に活性溶解が発生し、腐食速度が大きくなることが分かった。一方、高Cr$$_{rm eff}$$と比較的高濃度の硝酸、あるいは酸化性イオンの添加の組み合わせは不働態化を促進し、腐食速度を低下させることが分かった。


Oxidation kinetics of Zry-4 fuel cladding in mixed steam-air atmospheres at temperatures of 1273 - 1473 K

Negyesi, M.; 天谷 政樹

Journal of Nuclear Science and Technology, 54(10), p.1143 - 1155, 2017/10


This paper deals with the oxidation behavior of Zry-4 nuclear fuel cladding tubes in mixed steam_air atmospheres at temperatures of 1273 and 1473 K. The main goal is to study the oxidation kinetics of Zry-4 fuel cladding in dependence on the air fraction in steam in the range from 0 up to 100%. The purpose of this study is to provide experimental data suitable for an oxidation correlation applicable for thermomechanical analysis codes of nuclear power reactor under severe accidents. The influence of the air addition in steam on parameters of Zry-4 kinetic equation has been quantified using the results of weight gain measurements. At 1273 K, both pre-transient and post-transient regimes were treated. The results of weight gain measurements showed a strong dependence of the Zry-4 oxidation kinetics on the air fraction in steam, especially at 1473 and at 1273 K in the post-transient regime.


Development of unstructured mesh-based numerical method for sodium-water reaction phenomenon in steam generators of sodium-cooled fast reactors

内堀 昭寛; 渡部 晃*; 高田 孝; 大島 宏之

Journal of Nuclear Science and Technology, 54(10), p.1036 - 1045, 2017/10




Processes affecting long-term changes in $$^{137}$$Cs concentration in surface sediments off Fukushima

乙坂 重嘉

Journal of Oceanography, 73(5), p.559 - 570, 2017/10




Horizontal and vertical distributions of $$^{137}$$Cs in seabed sediments around the river mouth near Fukushima Daiichi Nuclear Power Plant

鶴田 忠彦; 原田 久也*; 御園生 敏治; 松岡 稔幸; 程塚 保行*

Journal of Oceanography, 73(5), p.547 - 558, 2017/10



Preface "Radionuclides in coastal sediments after the accident of Fukushima Daiichi Nuclear Power Plant; Distribution, dynamics and fate"

長尾 誠也*; 乙坂 重嘉; 帰山 秀樹*

Journal of Oceanography, 73(5), P. 527, 2017/10

福島第一原子力発電所事故から5年以上が経過し、海洋環境においても多くの調査研究が進められてきた。海底堆積物中の放射性セシウムの水平分布、時系列変動については、2011年5月より、主に宮城県・福島県・茨城県・千葉県沿岸域でのモニタリング調査が続けられている。しかしながら、事故由来放射性核種による海底堆積物及び海底付近の生態系への影響評価は、その局所依存性や観測の困難さ等により、他の環境調査に比べて遅れていた。今回、「Journal of Oceanography」誌において標題の特集セクションを組み、河口,沿岸及び沖合海域における海底堆積物中の放射性セシウムの濃度分布や、その数年規模での変化傾向と要因についての4報の論文を掲載した。本解説は、その特集の企画意図を示すとともに、内容を概観するものである。


Sources of $$^{137}$$Cs fluvial export from a forest catchment evaluated by stable carbon and nitrogen isotopic characterization of organic matter

武藤 琴美; 安藤 麻里子; 小嵐 淳; 竹内 絵里奈; 西村 周作; 都築 克紀; 松永 武*

Journal of Radioanalytical and Nuclear Chemistry, 314(1), p.403 - 411, 2017/10




Uranium age-dating using in-situ isotope ratios by thermal ionization mass spectrometry for nuclear forensics

大久保 綾子; 篠原 伸夫; 間柄 正明

Journal of Radioanalytical and Nuclear Chemistry, 314(1), p.231 - 234, 2017/10




鈴木 裕士; 楠 浩一*; 兼松 学*; 向井 智久*

コンクリート構造物の補修、補強、アップグレード論文報告集, 17, p.179 - 184, 2017/10



Study on a unified criterion for preventing plastic strain accumulation due to long distance travel of temperature distribution

岡島 智史; 若井 隆純; 川崎 信史

Mechanical Engineering Journal (Internet), 4(5), p.16-00641_1 - 16-00641_11, 2017/10

The prevention of excessive deformation by thermal ratcheting is important in the design of high-temperature components of fast breeder reactors (FBR). As a result of experimental study that simulated the fast breeder reactor vessel nearby the coolant surface, it was reported that long distance traveling of temperature distribution causes new type of thermal ratcheting, even if there is no primary stress. In this paper, we propose a simple screening criterion to prevent continuous accumulation of plastic strain derived from long distance traveling of temperature distribution. The major cause of this ratcheting mechanism is lack of residual stress that brings shakedown behavior at the center of yielding area. Because the residual stresses are derived from constraint against the elastic part, we focused on the distance from the center of yielding area to the elastic region. So, the proposed criterion restricts the axial length of the area with full-section yield state, which is the double of the above distance. We validated the proposed criterion based on finite element analyses using elastic-perfectly plastic material. As the result of the validation analyses, we confirmed that the accumulation of the plastic strain saturates before 2nd cycles in the cases that satisfy the proposed criterion, regardless of the shape of temperature distribution.



丸山 信一郎*; 綿谷 聡*

三井住友建設技術研究開発報告, (15), p.107 - 112, 2017/10



A Quasi-classical trajectory calculation for the cesium exchange reaction of $$^{133}$$CsI (v = 0, j = 0) + $$^{135}$$Cs $$rightarrow$$ $$^{133}$$Cs + I$$^{135}$$Cs

小林 孝徳*; 松岡 雷士*; 横山 啓一

日本エネルギー学会誌, 96(10), p.441 - 444, 2017/10

セシウム交換反応$$^{133}$$CsI (v=0, j=0) + $$^{135}$$Cs $$rightarrow$$ $$^{133}$$Cs + I$$^{135}$$Csの反応断面積を調べるため、ab initio分子軌道法計算により作成したポテンシャルエネルギー面を用いた準古典的トラジェクトリー計算を行った。ポテンシャルエネルギー面から反応中間体Cs$$_{2}$$Iの生成に入口障壁がないこと、2つのCsI結合が等価であることが明らかになった。トラジェクトリー計算により反応断面積は衝突エネルギーの増加と共に単調増加することが分かった。CsI分子の初期内部状態がv=0, j=0の場合の反応速度定数は500-1200Kの温度範囲で3$$times$$10$$^{-10}$$cm$$^{3}$$ molecule$$^{-1}$$s$$^{-1}$$程度と見積もられ、わずかながら負の温度依存性が見られた。


核データ研究の最前線; たゆまざる真値の追及、そして新たなニーズへ応える為に,1; 多様化する原子核工学と核データのニーズ

須山 賢也; 国枝 賢; 深堀 智生; 千葉 豪*

日本原子力学会誌, 59(10), p.598 - 602, 2017/10




古田 琢哉

日本保健物理学会ホームページ(インターネット), 2 Pages, 2017/10



A Numerical simulation method for molten material behavior in nuclear reactors

山下 晋; 伊奈 拓也; 井戸村 泰宏; 吉田 啓之

Nuclear Engineering and Design, 322, p.301 - 312, 2017/10




Transmutation effects on long-term Cs retention in phyllosilicate minerals from first principles

Sassi, M.*; 奥村 雅彦; 町田 昌彦; Rosso, K. M.*

Physical Chemistry Chemical Physics, 19(39), p.27007 - 27014, 2017/10




Self-learning Monte Carlo method; Continuous-time algorithm

永井 佑紀; Shen, H.*; Qi, Y.*; Liu, J.*; Fu, L.*

Physical Review B, 96(16), p.161102_1 - 161102_6, 2017/10




Quantum twin spectra in nanocrystalline silicon

松本 貴裕*; 大原 高志; 杉本 秀彦*; Bennington, S. M.*; 池田 進*

Physical Review Materials (Internet), 1(5), p.051601_1 - 051601_6, 2017/10

We identified twin split scattering spectra in hydrogen-terminated nanocrystalline silicon by using inelastic neutron scattering spectroscopy. A standard theoretical analysis based on the localized wave function of hydrogen in not sufficient to explain this duality. We show that this duality originates from the cooperative motion of hydrogen and silicon.


Benchmarking of flux-driven full-F gyrokinetic simulations

朝比 祐一*; Grandgirard, V.*; 井戸村 泰宏; Garbet, X.*; Latu, G.*; Sarazin, Y.*; Dif-Pradalier, G.*; Donnel, P.*; Ehrlacher, C.*

Physics of Plasmas, 24(10), p.102515_1 - 102515_17, 2017/10



Global kinetic simulations of neoclassical toroidal viscosity in low-collisional perturbed tokamak plasmas

松岡 清吉; 井戸村 泰宏; 佐竹 真介*

Physics of Plasmas, 24(10), p.102522_1 - 102522_9, 2017/10




Report on OPIC Laser Solutions for Space and the Earth (LSSE 2017)

戎崎 俊一*; 和田 智之*; 斎藤 徳人*; 藤井 隆*; 西村 昭彦

レーザー研究, 45(10), p.664 - 665, 2017/10




友田 陽*; 関戸 信彰*; 徐 平光; 川崎 卓郎; Harjo, S.; 田中 雅彦*; 篠原 武尚; Su, Y.; 谷山 明*

鉄と鋼, 103(10), p.570 - 578, 2017/10


Various methods were employed to measure the austenite volume fraction in a 1.5Mn-1.5Si-0.2C steel. It has been confirmed that the volume fractions determined by transmission electron microscopy, scanning electron microscopy/electron back scatter diffraction, X-ray diffraction and neutron diffraction exhibit a general trend to become larger in this order, although the values obtained by X-ray and neutron diffraction are similar in the present steel because austenite is relatively stable. The austenite volume fractions determined by diffraction methods have been found to be affected by the measuring specimen direction, i.e., texture, even by applying the conventional correcting procedure. To avoid this influence, it is recommended to measure both of volume fraction and texture simultaneously using neutron diffraction. Although synchrotron X-ray shows higher angle resolution, its small incident beam size brings poor statistic reliability. The influence of texture cannot be avoided for transmission Bragg edge measurement, either, which must be overcome to realize 2D or 3D volume fraction mapping.


$$^{107}$$PdのICP-MS測定のためのレーザー誘起光還元法による非接触・選択的パラジウム分離; 分離条件とPd回収率の関係

蓬田 匠; 浅井 志保; 佐伯 盛久*; 半澤 有希子; 堀田 拓摩; 江坂 文孝; 大場 弘則*; 北辻 章浩

分析化学, 66(9), p.647 - 652, 2017/09


ウランの核分裂生成物の一つである$$^{107}$$Pdは、半減期が約650万年と長く、長期間に渡り放射線を放出して人体に影響を及ぼす可能性があることから、高レベル放射性廃液(HLLW)中の存在量を正確に把握する必要がある。しかし、これまでその存在量の実測報告例はない。本研究では、遠隔・非接触分離が可能なレーザー誘起光還元法のHLLWへの適用を念頭に、HLW模擬液を用いて種々の分離条件がPd回収率に与える影響を検討した。Pdの回収率は、還元剤として作用するエタノール濃度、レーザー光の照射時間とパルスエネルギーに依存し、それぞれ40%、20分、100mJとした場合に60%となった。また、Pd濃度0.24$$mu$$g mL$$^{-1}$$から24$$mu$$g mL$$^{-1}$$の広い濃度範囲において、主要な放射能源やスペクトル干渉源となる元素を99.5%以上の割合で除去し、Pdを高純度に分離できることを明らかにした。本条件によれば、レーザー誘起光還元法はHLLWなど実際の放射性廃棄物に含まれる$$^{107}$$PdのICP-MS測定前処理法として、十分に適用可能である。



仲井 悟

デコミッショニング技報, (56), p.14 - 28, 2017/09




手塚 将志; 樽田 泰宜; 香田 有哉

デコミッショニング技報, (56), p.46 - 54, 2017/09




遠山 伸一; 峰原 英介*

デコミッショニング技報, (56), p.55 - 65, 2017/09




佐伯 盛久*; 田口 富嗣*; 大場 弘則*; 松村 大樹; 辻 卓也; 蓬田 匠

電気学会研究会資料,電子材料研究会(EFM-17-010$$sim$$021), p.15 - 18, 2017/09




白瀬 光泰*; 安部 章正*; 名合 牧人*; 石井 英一; 青柳 和平; 若杉 伸一*

土木学会平成29年度全国大会第72回年次学術講演会講演概要集(DVD-ROM), p.1795 - 1796, 2017/09



Deuteron nuclear data for the design of accelerator-based neutron sources: Measurement, model analysis, evaluation, and application

渡辺 幸信*; 金 政浩*; 荒木 祥平*; 中山 梓介; 岩本 修

EPJ Web of Conferences (Internet), 146, p.03006_1 - 03006_6, 2017/09



Development of a code system DEURACS for theoretical analysis and prediction of deuteron-induced reactions

中山 梓介; 河野 広*; 渡辺 幸信*; 岩本 修; Ye, T.*; 緒方 一介*

EPJ Web of Conferences (Internet), 146, p.12025_1 - 12025_4, 2017/09


近年、重陽子加速器を使った大強度中性子源が様々な応用に対して提案されている。このような中性子源の設計のためには、高精度かつ広範な重陽子核データライブラリが必要不可欠である。それゆえ、我々はDEURACS (DEUteron-induced Reaction Analysis Code System)という、重陽子入射反応の解析と理論予測用の統合コードシステムを開発している。本研究では、$$(d,xn)$$反応の解析をこれまでよりも高い100MeV近傍まで拡張した上、DEURACSを80および100MeVにおける$$(d,xd)$$反応にも適用した。その結果、DEURACSの計算値は$$(d,xn)$$および$$(d,xd)$$反応の二重微分断面積の実験値を良く再現した。


Neutron production in deuteron-induced reactions on Li, Be, and C at an incident energy of 102 MeV

荒木 祥平*; 渡辺 幸信*; 北島 瑞希*; 定松 大樹*; 中野 敬太*; 金 政浩*; 岩元 洋介; 佐藤 大樹; 萩原 雅之*; 八島 浩*; et al.

EPJ Web of Conferences (Internet), 146, p.11027_1 - 11027_4, 2017/09

近年、核融合マテリアルの損傷の研究、ホウ素中性子捕捉療法、医療用放射性核種生成等の中性子源として、重陽子入射反応の利用が考えられている。しかし、入射重陽子エネルギー60MeVを超える領域では、重陽子入射反応の理論モデルの検証に必要な実験値はほとんどない。そこで、本研究では、大阪大学核物理研究センター(RCNP)において、100MeVの重陽子入射によるリチウム、ベリリウム及び炭素の中性子生成二重微分断面積(DDX)の測定を行った。測定角度は、0$$^{circ}$$から25$$^{circ}$$の間の6角度とし、飛行時間法により中性子エネルギーを導出した。中性子検出器に、大きさの異なる3台の液体有機シンチレータNE213(直径及び厚さが2インチ, 5インチ, 10インチ)を用い、中性子の飛行距離をそれぞれ7, 24, 74mとした。中性子検出効率は、SCINFUL-QMDコードの計算により導出した。実験結果から、中性子エネルギー強度分布は、重陽子入射エネルギーの半分のエネルギーにおいて、重陽子ブレークアップ過程に起因するなだらかなピーク構造を持つことがわかった。また、PHITSによる計算値は、理論モデルの不備から実験値をよく再現しないことがわかった。


FRENDY; A New nuclear date processing system being developed at JAEA

多田 健一; 長家 康展; 国枝 賢; 須山 賢也; 深堀 智生

EPJ Web of Conferences (Internet), 146, p.02028_1 - 02028_5, 2017/09

原子力機構では、新たな核データ処理システムFENDY(FRom Evaluated Nuclear Data libralY to any application)の開発を開始した。本発表では、FRENDYの概要と同時にFRENDYを使用した連続エネルギーモンテカルロコードMVP, PHITS及びMCNP用の断面積作成とその妥当性検証結果について説明する。


Nuclear data evaluation of long-lived fission products; Microscopic vs. phenomenological optical potentials

湊 太志; 岩本 修; 蓑茂 工将*; 緒方 一介*; 岩本 信之; 国枝 賢; 古立 直也

EPJ Web of Conferences (Internet), 146, p.12032_1 - 12032_4, 2017/09



Technical developments for accurate determination of amount of samples used for TOF measurements

寺田 和司; 中尾 太郎; 中村 詔司; 木村 敦; 岩本 修; 原田 秀郎; 高宮 幸一*; 堀 順一*

EPJ Web of Conferences (Internet), 146, p.03019_1 - 03019_4, 2017/09




Application of modified REFIT code for J-PARC/MLF to evaluation of neutron capture cross section on $$^{155,157}$$Gd

水山 一仁; 岩本 信之; 岩本 修; 長谷美 宏幸*; 木野 幸一*; 木村 敦; 鬼柳 善明*

EPJ Web of Conferences (Internet), 146, p.11042_1 - 11042_4, 2017/09



Neutron capture cross section measurements of $$^{120}$$Sn, $$^{122}$$Sn and $$^{124}$$Sn with the array of Ge spectrometer at the J-PARC/MLF/ANNRI

木村 敦; 原田 秀郎; 中村 詔司; 藤 暢輔; 井頭 政之*; 片渕 竜也*; 水本 元治*; 堀 順一*

EPJ Web of Conferences (Internet), 146, p.11031_1 - 11031_4, 2017/09

Accurate neutron capture cross section data of $$^{126}$$Sn, which is one of the most important long-lived fission products (LLFPs), is required in the study of transmutation of radioactive waste. However, there is only one experimental data at the thermal energy. A $$^{126}$$Sn sample for a nuclear data experiment contaminated with a large amount of tin stable isotopes, $$^{115, 117-120, 122, 124}$$Sn, because these stable isotopes also have fission yields. These isotopes have large effects on neutron-capture cross-section measurements for $$^{126}$$Sn. To obtain accurate cross-section data for $$^{126}$$Sn, a series of neutron-capture cross-section measurements of all the tin stable isotopes are required. Therefore, the measurements of all tin stable isotopes have been started with Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI) of Materials and Life science experimental Facility (MLF) in Japan Proton Accelerator Research Complex (J-PARC). In this presentation, preliminary results of the neutron-capture cross-section measurements of $$^{120, 122, 124}$$Sn are reported in the neutron energy region from 10 meV to 2 keV.


Status of the JENDL project

岩本 修; 柴田 恵一; 岩本 信之; 国枝 賢; 湊 太志; 市原 晃; 中山 梓介

EPJ Web of Conferences (Internet), 146, p.02005_1 - 02005_6, 2017/09

The latest version of the general purpose file JENDL-4.0 was released in 2010 with enhancing data of fission products and minor actinides. After that, the neutron energy range of JENDL-4.0 were extended up to 200 MeV adding proton induced reaction data. They were compiled as JENDL-4.0/HE and released in 2015. An activation cross section library for decommission of nuclear reactor, JENDL/AD-2016, is under development and will be released by 2017. It will contain neutron reaction data for approximately 300 nuclides in energy range of $$10^{-5}$$ eV to 20 MeV including isomer production cross sections. Evaluation of nuclear data for the next version of the general purpose file is also in progress. It is planned to be released by 2022. Several new evaluations mainly for fission products that had not been updated in JENDL-4.0 were already done. Data for light nuclei and structure material will be updated. Minor actinides data are still important to develop transmutation system of nuclear waste. They will be updated using new measurements especially done in J-PARC. Status of the JENDL project in developing the general and special purpose files will be presented.


Status of the R-matrix code AMUR toward a consistent cross-section evaluation and covariance analysis for the light nuclei

国枝 賢

EPJ Web of Conferences (Internet), 146, p.12029_1 - 12029_4, 2017/09



Inter-comparison of Hauser-Feshbach model codes toward better actinide evaluations

Capote, R.*; Hilaire, S.*; 岩本 修; 河野 俊彦*; Sin, M.*

EPJ Web of Conferences (Internet), 146, p.12034_1 - 12034_4, 2017/09

The Hauser-Feshbach codes that include a pre-equilibrium model have been playing for years a central role in producing evaluated nuclear reaction data files. The codes, such as Empire, TALYS, CCONE, and CoH$$_{3}$$, have been and are still actively upgraded in order to better understand nuclear reaction mechanisms by sharing and exchanging theoretical knowledge as well as computational techniques between actors involved in their development. Albeit the framework of the model codes aforementioned is quite similar, implementation of the reaction models as well as computational techniques adopted may produce some differences in the calculated results. The IAEA Nuclear Data Section conducts one of such inter-organizational collaborations, and defined some exercises to compare the Hauser-Feshbach codes developed for nuclear data evaluations, with a particular focus on the actinide evaluations. We report here the results of Hauser-Feshbach calculations for neutron induced reactions on actinide nuclei using the input parameters defined in the IAEA report [Capote et al., INDC-NDS-0654 (2014)], and discuss the differences among these codes.


Developments of a new data acquisition system at ANNRI

中尾 太郎; 寺田 和司; 木村 敦; 中村 詔司; 岩本 修; 原田 秀郎; 片渕 竜也*; 井頭 政之*; 堀 順一*

EPJ Web of Conferences (Internet), 146, p.03021_1 - 03021_4, 2017/09


J-PARC物質・生命科学実験施設ANNRIビームラインのデータ収集系更新作業が行われた。MLFのビームパワーは2008年に比較して2015年には20倍以上となり、ビーム量の増大によりビームラインユーザーはより高統計の実験データを取得できるようになった。ビームパワー増大に対応するため、ANNRIにおけるGe検出器アレイのデータ収集システムが更新された。データ収集システムは同時に、中性子全断面積測定のために整備されているLi glass検出器の信号取得のためにも用いられる予定である。コミッショニング実験が0.1mm厚の金サンプルを用いてJ-PARCの500kW陽子ビームを用いて行われた。捕獲断面積および全断面積測定両方について飛行時間法の適用性が試験された。Ge検出器アレイについて、ADCおよびTDCの非線形性、エネルギー分解能、多チャンネルコインシデンスおよび不感時間の性能が測定された。Ge検出器の不感時間は従来のデータ収集システムに比較して、少しのエネルギー分解能劣化を許容すれば1/4になっていた。


Research and development for accuracy improvement of neutron nuclear data on minor actinides

原田 秀郎; 岩本 修; 岩本 信之; 木村 敦; 寺田 和司; 中尾 太郎; 中村 詔司; 水山 一仁; 井頭 政之*; 片渕 竜也*; et al.

EPJ Web of Conferences (Internet), 146, p.11001_1 - 11001_6, 2017/09


A nuclear data project entitled Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC) is being performed in Japan. The objective of the project is to improve accuracy of neutron nuclear data for minor actinides and some fission products, which is required for developing innovative nuclear system transmuting these nuclei. Following research items have been conducted to achieve the objective: (1) Measurements of thermal neutron capture cross-sections by activation methods, (2) High-precision quantifications of shielded sample amounts used for TOF measurement, (3) Resonance parameter determinations at J-PARC/ANNRI and KURRI/LINAC, (4) Extension of capture cross sections to high energy neutrons at J-PARC/ANNRI, (5) High quality evaluation based on iterative communication with experimenters. The achievement of the project is presented.


Improving nuclear data accuracy of $$^{241}$$ Am and $$^{237}$$ Np capture cross sections

$v{Z}$erovnik, G.*; Schillebeeckx, P.*; Cano-Ott, D.*; Jandel, M.*; 堀 順一*; 木村 敦; Rossbach, M.*; Letourneau, A.*; Noguere, G.*; Leconte, P.*; et al.

EPJ Web of Conferences (Internet), 146, p.11035_1 - 11035_4, 2017/09


There is a serious gap between required accuracy and current accuracy on nuclear data for developing innovative nuclear reactor systems. To bridge this gap, an international joint activity entitled Improving Nuclear Data Accuracy of $$^{241}$$Am and $$^{237}$$Np capture cross sections (INDA) has being performed under WPEC. In this joint study, the forefront knowledge of energy dependent cross section measurements, spectrum averaged experiments, relevant nuclear structure data, and evaluations are intended to be integrated on the capture cross sections of $$^{241}$$Am and $$^{237}$$Np. From the joint study, it was shown that integration of knowledge from the independent specialities enables us not only to crosscheck between data obtained by different techniques but also to improve the measurement accuracy of each other.


Analysis of energy resolution in the KURRI-LINAC pulsed neutron facility

佐野 忠史*; 堀 順一*; 高橋 佳之*; 八島 浩*; Lee, J.*; 原田 秀郎

EPJ Web of Conferences (Internet), 146, p.03031_1 - 03031_3, 2017/09


We carried out Monte Carlo calculation to provide energy resolution of pulsed neutron beam for TOF measurements in the KURRI-LINAC pulsed neutron facility. The calculations were performed for moderated neutron flux at the energy range from 0.01 eV to 20 MeV. As the result, we obtained the energy resolutions ($$Delta$$E/E) in the epi-thermal region. For example, the energy resolutions were 1.0% in the neutron energy of 1.0 eV, 1.1% in 100.0 eV and 1.7% in 1.0 keV.


High precision analysis of isotopic composition for samples used for nuclear cross-section measurements

芝原 雄司*; 堀 順一*; 高宮 幸一*; 藤井 俊行*; 福谷 哲*; 佐野 忠史*; 原田 秀郎

EPJ Web of Conferences (Internet), 146, p.03028_1 - 03028_4, 2017/09

For the accuracy improvement of nuclear data of minor actinides and long-lived fission products in AIMAC project, high quality data of the isotopic composition of samples are indispensable. The objective of this research is to obtain the isotopic composition data of samples contributing to the analysis of nuclear cross-section measurement data by mass spectrometry etc. In this study, we analyzed the isotopic composition of two Am samples ($$^{241}$$ Am sample and $$^{243}$$ Am sample) mainly by the thermal ionization mass spectrometry (TIMS). In addition to the TIMS, Am samples were also analyzed by $$alpha$$-spectrometry. In the analysis by both methods, the impurities such as $$^{239}$$Pu, $$^{240}$$Pu, $$^{242}$$Cm and$$^{244}$$Cm were also observed. The results of these analyses are presented together with the developed high precision analytical method.


Experimental analysis of neutron and background $$gamma$$-ray energy spectra of 80-400 MeV $$^{7}$$Li(p,n) reactions under the quasi-monoenergetic neutron field at RCNP, Osaka University

岩元 洋介; 佐藤 達彦; 佐藤 大樹; 萩原 雅之*; 八島 浩*; 増田 明彦*; 松本 哲郎*; 岩瀬 広*; 嶋 達志*; 中村 尚司*

EPJ Web of Conferences (Internet), 153, p.08019_1 - 08019_3, 2017/09



Delayed $$gamma$$-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

小泉 光生; Rossi, F.; Rodriguez, D.; 高峰 潤; 瀬谷 道夫; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EPJ Web of Conferences (Internet), 146, p.09018_1 - 09018_4, 2017/09

Along with the global increase of applications using nuclear materials (NM), the requirements to nuclear security and safeguards for the development of effective characterization methods are growing. Mass verification of NM of low radioactivity is performed using passive non-destructive analysis (NDA) techniques whereas destructive analysis (DA) techniques are applied for accurate analysis of nuclide composition. In addition to the characterization by passive NDA, a sample can be further characterized by active NDA techniques. An active neutron NDA system equipped with a pulsed neutron generator is currently under development for studies of NDA methods. Among the methods DGS uses the detection of decay $$gamma$$-rays from fission products (FP) to determine ratios of fissile nuclides present in the sample. A proper evaluation of such $$gamma$$-ray spectra requires integration of nuclear data such as fission cross-sections, fission yields, half-lives, decay chain patterns, and decay $$gamma$$-ray emission probabilities. The development of the DGS technique includes experimental verification of some nuclear data of fissile materials, as well as development of the device. This presentation will be a brief introduction of the active neutron NDA project and an explanation of the DGS development program.


Neutron resonance analysis for nuclear safeguards and security applications

Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*; 原田 秀郎; 北谷 文人; 小泉 光生; 土屋 晴文

EPJ Web of Conferences (Internet), 146, p.09002_1 - 09002_4, 2017/09

Neutron-induced reactions can be used to study the properties of nuclear materials in the field of nuclear safeguards and security. The elemental and isotopic composition of these materials can be determined by using the presence of resonance structures in the reaction cross sections as fingerprints. This idea is the basis of two non-destructive analytical techniques which have been developed at the GELINA neutron time-of-flight facility of the JRC-IRMM: Neutron Resonance Capture Analysis (NRCA) and Neutron Resonance Transmission Analysis (NRTA). A full quantitative validation of the NRTA technique was obtained by determining the areal densities of enriched reference samples used for safeguards applications with an accuracy better than 1%. Moreover, a combination of NRTA and NRCA has been proposed for the characterisation of particle-like debris of melted fuel formed in severe nuclear accidents. In order to deal with the problems due to the diversity in shape and size of these samples and the presence of strong absorbing matrix materials, new capabilities have been implemented in the resonance shape analysis code REFIT. They have been validated by performing a blind test in which the elemental abundance of a combined sample composed of unknown quantities of materials such as cobalt, tungsten, rhodium or gold was determined with accuracies better than 2%.


Characterization of the PTW 34031 ionization chamber (PMI) at RCNP with high energy neutrons ranging from 100 - 392 MeV

Theis, C.*; Carbonez, P.*; Feldbaumer, E.*; Forkel-Wirth, D.*; Jaegerhofer, L.*; Pangallo, M.*; Perrin, D.*; Urscheler, C.*; Roesler, S.*; Vincke, H.*; et al.

EPJ Web of Conferences (Internet), 153, p.08018_1 - 08018_5, 2017/09



Updating source term and atmospheric dispersion simulations for the dose reconstruction in Fukushima Daiichi Nuclear Power Station accident

永井 晴康; 寺田 宏明; 都築 克紀; 堅田 元喜; 太田 雅和; 古野 朗子; 朱里 秀作

EPJ Web of Conferences (Internet), 153, p.08012_1 - 08012_7, 2017/09



Recent improvements of particle and heavy ion transport code system: PHITS

佐藤 達彦; 仁井田 浩二*; 岩元 洋介; 橋本 慎太郎; 小川 達彦; 古田 琢哉; 安部 晋一郎; 甲斐 健師; 松田 規宏; 奥村 啓介; et al.

EPJ Web of Conferences (Internet), 153, p.06008_1 - 06008_6, 2017/09




Shielding experiments of concrete and iron for the 244 MeV and 387 MeV quasi-mono energetic neutrons using a Bonner sphere spectrometer (at RCNP, Osaka Univ.)

松本 哲郎*; 増田 明彦*; 西山 潤*; 岩瀬 広*; 岩元 洋介; 佐藤 大樹; 萩原 雅之*; 八島 浩*; 八島 浩*; 嶋 達志*; et al.

EPJ Web of Conferences (Internet), 153, p.08016_1 - 08016_3, 2017/09



Neutron spectrometry and dosimetry in 100 and 300 MeV quasi-mono-energetic neutron field at RCNP, Osaka University, Japan

Mares, V.*; Trinkl, S.*; 岩元 洋介; 増田 明彦*; 松本 哲郎*; 萩原 雅之*; 佐藤 大樹; 八島 浩*; 嶋 達志*; 中村 尚司*

EPJ Web of Conferences (Internet), 153, p.08020_1 - 08020_3, 2017/09



Evaluation of neutron total and capture cross sections on $$^{99}$$Tc in the unresolved resonance region

岩本 信之; 片渕 竜也*

EPJ Web of Conferences (Internet), 146, p.02049_1 - 02049_4, 2017/09

The reliable nuclear data on Technetium-99 ($$^{99}$$Tc) are indispensable for wide energy range up to a few MeV, in order to develop environmental load reducing technology. Nevertheless, it is found that the total cross sections of evaluated libraries show large difference in the energies above the resolved resonance to 1 MeV due to no available experimental data. The total cross section was calculated by the coupled-channels optical model. In order to constrain the total cross section in the unresolved resonance region we adopted neutron strength function derived from the resolved resonance data of JENDL-4.0, together with experimental data above 1 MeV. The calculation of capture cross section was done by using the CCONE code. The resonance spacing was derived from the resonance data and used to fix the level density parameter. The present evaluation suggests that the total cross section is different from that of JENDL-4.0. In this presentation, the obtained total and capture cross sections will be compared and discussed with those of evaluated libraries.


Inter-comparison of Dose Distributions Calculated by FLUKA, GEANT4, MCNP, and PHITS for Proton Therapy

Yang, Z.-Y.*; Tsai, P.-E.; Lee, S.-C.*; Liu, Y.-C.*; Chen, C.-C.*; 佐藤 達彦; Sheu, R.-J.*

EPJ Web of Conferences (Internet), 153, p.04011_1 - 04011_8, 2017/09


広く普及している4つの放射線挙動解析コードGEANT4, FLUKA, MCNPX及びPHITSについて、ペンシルビーム照射条件により陽子治療計画への適用性を検証した。最初の条件として、水ファントムへの単色陽子照射を仮定し、各コードによる深度線量曲線の積分値(IDDCs)を比較した。2つ目のケースとして、エネルギーが分布する陽子ビーム照射に関するIDDCsを検証した。これらの結果は、米国ニュージャージのProCure陽子治療センターにおける実験結果と比較した。実測値に対する各コードによる結果は一定でなく、ファントム中の浅い領域やBraggピーク付近で線量の計算値で差が生じることを確認した。この他、3つ目ケースとして、拡大ブラッグピーク(SOBP)の調査を進めている。


Influence of the neutron transport tube on neutron resonance densitometry

北谷 文人; 土屋 晴文; 小泉 光生; 高峰 潤; 堀 順一*; 佐野 忠史*

EPJ Web of Conferences (Internet), 146, p.09032_1 - 09032_3, 2017/09

The use of a short flight path is effective in the neutron resonance analysis. On the other hand, such a short path would reduce a time resolution in Time-Of-Flight (TOF) measurements. In order to investigate the effect of neutron flight-path length, we carried out Neutron Resonance Transmission Analysis (NRTA) experiments with a short neutron flight path at the Kyoto University Research Reactor Institute - Linear Accelerator (KURRI-LINAC). In measurements of Neutron Resonance Densitometry, the quantity of nuclear materials is determined from TOF spectra obtained in the neutron energy range below 30 eV. Performing NRTA experiments with a 7-m flight path at KURRI-LINAC, we examined effects of flight path and pulse width on a TOF spectrum. A resonance dip of $$^{183}$$W at 27 eV in a TOF spectrum was successfully observed with an electron pulse width less than 2 $$mu$$s. In this presentation, we will discuss importance of the pulse width and short flight path to study design of a compact TOF facility to quantify nuclear materials.


Important comments on KERMA factors and DPA cross-section data in ACE files of JENDL-4.0, JEFF-3.2 and ENDF/B-VII.1

今野 力; 多田 健一; 権 セロム*; 太田 雅之*; 佐藤 聡*

EPJ Web of Conferences (Internet), 146, p.02040_1 - 02040_4, 2017/09

これまでに核データライブラリーの公式のACEファイルに内蔵されている多くの核種のKERMA係数、DPA断面積が以下の理由で異なっていることを指摘してきた。(1)核データの誤り、(2)NJOYのバグ、(3)非常に大きなヘリウム生成断面積、(4)mf6 mt102データ、(5)2次粒子のエネルギー角度分布データがないこと。今回、JENDL-4.0, ENDF/B-VII.1, JEFF-3.2のKERMA係数, DPA断面積をより詳細に調べた。その結果、核データリブラリー間でのKERMA係数、DPA断面積の差の新たな原因を見出した。新たな原因は、以下に分類される。2次荷電粒子データがないこと、2次$$gamma$$線データがないこと、妥当でない2次$$gamma$$線スペクトル、妥当でない粒子生成収率、捕獲反応をmf12-15 mt3データに格納すること。これらの原因のいくつかはNJOYコードが対応していないことによると思われる。問題のあるJENDL-4.0, ENDF/B-VII.1, JEFF-3.2のACEファイルは本研究をもとに改訂すべきである。


JENDL-4.0/HE benchmark test with concrete and iron shielding experiments at JAEA/TIARA

今野 力; 松田 規宏; 権 セロム*; 太田 雅之*; 佐藤 聡*

EPJ Web of Conferences (Internet), 153, p.01024_1 - 01024_6, 2017/09




Improvement of gross theory of beta-decay for application to nuclear data

小浦 寛之; 吉田 正*; 橘 孝博*; 千葉 敏*

EPJ Web of Conferences (Internet), 146, p.12003_1 - 12003_4, 2017/09


A theoretical study of $$beta$$ decay and delayed neutron has been carried out with a global $$beta$$-decay model: the gross theory. In a fissioning nucleus, neutrons are produced by the $$beta$$ decay of neutron-rich fission fragments. This is known as delayed neutrons. The gross theory of the $$beta$$ decay is based on a consideration of the sum rule of the $$beta$$-strength function, and gives reasonable results of $$beta$$-decay rates and delayed neutron in the entire nuclear mass region. We re-analyze and improve the theory on the strength functions and one-particle level densities. We focus on the spin-parity of decaying nucleus, and a hindrance treatment is introduced for the allowed transition on parity-mismatching nuclei. By using the improved gross theory, the ability of theoretically reproduction (and also prediction) on $$beta$$-decay rates, delayed-neutron emission probabilities, decay heat, will be discussed. In the process, we make a new code of the gross theory of $$beta$$- decay including the improved parts. We will show the code, which can be distributed for the nuclear data community.


Characterization of the n_TOF EAR-2 neutron beam

Chen, Y. H.*; Tassan-Got, L.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他130名*

EPJ Web of Conferences (Internet), 146, p.03020_1 - 03020_4, 2017/09




The $$^{33}$$S(n, $$alpha$$)$$^{30}$$Si cross section measurement at n_TOF-EAR2 (CERN); From 0.01 eV to the resonance region

Sabat$'e$-Gilarte, M.*; Praena, J.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他126名*

EPJ Web of Conferences (Internet), 146, p.08004_1 - 08004_4, 2017/09

CERNのn_TOF第2実験室において、$$^{10}$$B(n,$$alpha$$)を標準断面積として用い、$$^{33}$$S(n, $$alpha$$)$$^{30}$$Si反応断面積を測定した。本実験室では初めてとなる0.01eVから100keVまでの実験データを取得し、本データより0.01eVから10keVまでの中性子断面積を導出した。本反応は、$$^{10}$$B(n, $$alpha$$)反応とともに放射線療法への利用が期待されているが、従来報告された断面積値間には大きな差異がある。本研究により導出した断面積は、信頼性ある断面積評価に反映されることが期待される。


Dissemination of data measured at the CERN n_TOF facility

Dupont, E.*; 大塚 直彦*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他224名*

EPJ Web of Conferences (Internet), 146, p.07002_1 - 07002_4, 2017/09



New measurement of the $$^{242}$$Pu(n, $$gamma$$) cross section at n_TOF-EAR1 for MOX fuels; Preliminary results in the RRR

Lerendegui-Marco, J.*; Guerrero, C.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他115名*

EPJ Web of Conferences (Internet), 146, p.11045_1 - 11045_4, 2017/09




The Measurement programme at the neutron time-of-flight facility n_TOF at CERN

Gunsing, F.*; Aberle, O.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他147名*

EPJ Web of Conferences (Internet), 146, p.11002_1 - 11002_6, 2017/09



Measurement of the $$^{240}$$Pu(n,f) cross-section at the CERN n_TOF facility; First results from experimental area II (EAR-2)

Stamatopoulos, A.*; Tsinganis, A.*; Colonna, N.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他126名*

EPJ Web of Conferences (Internet), 146, p.04030_1 - 04030_4, 2017/09


The accurate knowledge of the neutron-induced fission cross-sections of actinides and other isotopes involved in the nuclear fuel cycle is essential for the design of advanced nuclear systems, such as Generation-IV nuclear reactors. Such experimental data can also provide the necessary feedback for the adjustment of nuclear model parameters used in the evaluation process, resulting in the further development of nuclear fission models. In the present work, the $$^{240}$$Pu(n,f) cross-section was measured at CERN n_TOF facility relative to the well-known $$^{235}$$U(n,f) cross section, over a wide range of neutron energies, from meV to almost MeV, using the time-of-flight technique and a set-up based on Micromegas detectors. This measurement was the first experiment to be performed at n_TOF new experimental area (EAR-2), which offers a significantly higher neutron flux compared to the already existing experimental area (EAR-1).Preliminary results as well as the experimental procedure, including a description of the facility and the data handling and analysis, are presented.


Monte Carlo simulations of the n_TOF lead spallation target with the Geant4 toolkit; A Benchmark study

Lerendegui-Marco, J.*; Cort$'e$s-Giraldo, M. A.*; Guerrero, C.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他114名*

EPJ Web of Conferences (Internet), 146, p.03030_1 - 03030_4, 2017/09

Monte Carlo (MC) simulations are an essential tool to determine fundamental features of a neutron beam, such as the neutron flux or the $$gamma$$ ray background, that sometimes can not be measured or at least not in every position or energy range. Until recently, the most widely used MC codes in this field had been MCNPX and FLUKA. However, the Geant4 toolkit has also become a competitive code for the transport of neutrons after the development of the native Geant4 format for neutron data libraries, G4NDL. In this context, we present the Geant4 simulations of the neutron spallation target of the n TOF facility at CERN, done with version 10.1.1 of the toolkit. The first goal was the validation of the intra-nuclear cascade models implemented in the code using, as benchmark, the characteristics of the neutron beam measured at the first experimental area (EAR1), especially the neutron flux and energy distribution, and the time distribution of neutrons of equal kinetic energy, the so-called Resolution Function. The second goal was the development of a Monte Carlo tool aimed to provide useful calculations for both the analysis and planning of the upcoming measurements at the new experimental area (EAR2) of the facility.


$$^7$$Be(n,$$alpha$$) and $$^7$$Be(n,p) cross-section measurement for the cosmological lithium problem at the n_TOF facility at CERN

Barbagallo, M.*; Colonna, N.*; Aberle, O.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他125名*

EPJ Web of Conferences (Internet), 146, p.01012_1 - 01012_4, 2017/09

The Cosmological Lithium Problem refers to the large discrepancy between the abundance of primordial $$^7$$Li predicted by the standard theory of Big Bang Nucleosynthesis and the value inferred from the so-called "Spite plateau" in halo stars. A possible explanation for this longstanding puzzle in Nuclear Astrophysics is related to the incorrect estimation of the destruction rate of $$^7$$Be, which is responsible for the production of 95% of primordial Lithium. While charged-particle induced reactions have mostly been ruled out, data on the $$^7$$Be(n,$$alpha$$) and $$^7$$Be(n,p) reactions are scarce or completely missing, so that a large uncertainty still affects the abundance of $$^7$$Li predicted by the standard theory of Big Bang Nucleosynthesis. Both reactions have been measured at the n_TOF facility at CERN, providing for the first time data in a wide neutron energy range._1


The n_TOF facility; Neutron beams for challenging future measurements at CERN

Chiaveri, E.*; Aberle, O.*; Andrzejewski, J.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他111名*

EPJ Web of Conferences (Internet), 146, p.03001_1 - 03001_4, 2017/09

The CERN n_TOF neutron beam facility is characterized by a very high instantaneous neutron flux, excellent TOF resolution at the 185m long flight path (EAR-1), low intrinsic background and coverage of a wide range of neutron energies, from thermal to a few GeV. The overall efficiency of the experimental program and the range of possible measurements has been expanded with the construction of a second experimental area (EAR-2), located 20m on the vertical of the n_TOF spallation target. This upgrade, which benefits from a neutron flux 30 times higher than in EAR-1, provides a substantial extension in measurement capabilities, opening the possibility to collect data on neutron cross-section of isotopes with short half-lives or available in very small amounts. We will discuss the innovative features of the EAR-2 neutron beam that make possible to perform very challenging measurements on short-lived radioisotopes or sub-mg samples, out of reach up to now at other neutron facilities around the world. Finally, the future perspectives of the facility will be presented.


Time-of-flight and activation experiments on $$^{147}$$Pm and $$^{171}$$Tm for astrophysics

Guerrero, C.*; Lerendegui-Marco, J.*; Domingo-Pardo, C.*; 原田 秀郎; 木村 敦; n_TOF Collaboration*; 他113名*

EPJ Web of Conferences (Internet), 146, p.01007_1 - 01007_4, 2017/09

The neutron capture cross section of several key unstable isotopes acting as branching points in the s-process are crucial for stellar nucleosynthesis studies, but they are very challenging to measure due to the difficult production of sufficient sample material, the high activity of the resulting samples, and the actual (n,$$gamma$$) measurement, for which high neutron fluxes and effective background rejection capabilities are required. Capture cross section of $$^{147}$$Pm and $$^{171}$$Tm have been measured for time-of-flight measurements at the CERN n_TOF facility using the 19 and 185m beam lines. Activation experiments on the same $$^{147}$$Pm and $$^{171}$$Tm targets with a high-intensity 30 keV quasi-Maxwellian flux of neutrons will be performed using the SARAF accelerator and the Liquid-Lithium Target (LiLiT) in order to extract the corresponding Maxwellian Average Cross Section (MACS). The status of these experiments and preliminary results will be presented and discussed as well.


The CIELO collaboration; Progress in international evaluations of neutron reactions on Oxygen, Iron, Uranium and Plutonium

Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Kahler, A. C.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Pigni, M.*; Dunn, M.*; Leal, L.*; et al.

EPJ Web of Conferences (Internet), 146, p.02001_1 - 02001_9, 2017/09


CIELO共同研究では中性子断面積データの改善及びこれまでの評価で見られた断面積の不一致を解決することを目的として、原子力の臨界性に大きな影響を与える5核種($$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U, $$^{239}$$Pu)の中性子断面積を評価している。この国際パイロットプロジェクトでは、経済協力開発機構・原子力機関・核データ評価国際協力ワーキングパーティに設置されたサブグループ40の下でIAEAからのサポートを受けて、実験並びに理論的な研究を活発に実施している。これらの研究を通じて測定データを精度よく反映し、さらに臨界性に関する積分テストで良い結果を示す新しい評価済ライブラリを開発している。


A New evaluation of the neutron data standards

Carlson, A. D.*; Pronyaev, V.*; Hale, G. M.*; Zhenpeng, C.*; Capote, R.*; Dur$'a$n, I.*; Hambsch, F.-J.*; 河野 俊彦*; 国枝 賢; 他13名*

EPJ Web of Conferences (Internet), 146, p.02025_1 - 02025_4, 2017/09


近年測定された新しい断面積測定値を反映させることにより、IAEA標準核データである$$^1$$H(n,n), $$^6$$Li(n,t), $$^{10}$$B(n,$$alphagamma$$), $$^{10}$$B(n,$$alpha$$), C(n,n), $$^{197}$$Au(n,$$gamma$$), $$^{235}$$U(n,f)及び$$^{238}$$U(n,f)反応断面積の更新を行った。また、Au(n,$$gamma$$)反応断面積については、従来の標準核データに格納されていたデータを低エネルギー側へ拡張した。さらに、$$^{209}$$Biや$$^{238}$$U等に対する高エネルギー核分裂断面積、熱中性子反応による$$^{235}$$Uの核分裂中性子スペクトルや$$^{252}$$Cf自発核分裂中性子スペクトル等のデータを標準断面積に準じる参考値として整備した。


An Evaluation method of reflectance spectra to be obtained by Hayabusa2 Near-Infrared Spectrometer (NIRS3) based on laboratory measurements of carbonaceous chondrites

松岡 萌*; 中村 智樹*; 大澤 崇人; 岩田 隆浩*; 北里 宏平*; 安部 正真*; 仲内 悠祐*; 荒井 武彦*; 小松 睦美*; 廣井 孝弘*; et al.

Earth, Planets and Space (Internet), 69(1), p.120_1 - 120_12, 2017/09




Prediction of chemical effects of Mo and B on the Cs chemisorption onto stainless steel

Di Lemma, F. G.; 山下 真一郎; 三輪 周平; 中島 邦久; 逢坂 正彦

Energy Procedia, 127, p.29 - 34, 2017/09




前川 藤夫; 佐々 敏信

エネルギーレビュー, 37(9), p.15 - 18, 2017/09




辻本 和文

エネルギーレビュー, 37(9), p.11 - 14, 2017/09



Analysis of external surface irregularities on Fukushima-derived fallout particles

Martin, P. G.*; 佐藤 志彦; Griffiths, I.*; Richards, D.*; Scott, T.*

Frontiers in Energy Research (Internet), 5, p.25_1 - 25_9, 2017/09

Three large high radioactivity particulate fragments, each several 100 $$mu$$m in diameter, have been recovered from the region immediately surrounding the Fukushima Daiichi Nuclear Power Plant. Through the application of high-resolution electron and ion-beam methods, this work has sought to investigate the structure and composition of this fibrous surface morphology. By evaluating this, a potential material source can be determined, alongside important information relating to the conditions/events at the time of the reactor explosions and catastrophic release of radioactive materials. The results of this study show that the fibrous features associated with these large radiocesium-containing particles share a common elemental composition. With respect to the surrounding particle, the fibers are enriched in Si, Cl, and Fe, while depleted in both Zn and Al. Based on composition, these fibers are ascribed to thermal insulating material used within the plant, which was sufficiently heated during the loss of coolant incident at the plant to be incorporated into the molten ejecta material that rapidly solidified upon quenching in air. Elemental analysis of these fibers does not reveal any evidence of leaching or the presence of actinide materials.


Evaluation of effective dose coefficient with variation of absorption fraction in gastrointestinal system for ingestion of radiocesium

Pratama, M. A.; 高原 省五; 波戸 真治*

保健物理, 52(3), p.200 - 209, 2017/09

本研究の目的は、胃腸管吸収率($$f_{1}$$ 値)の変動が預託実効線量換算係数にもたらす変化を特定することに加えて、年齢別に異なる$$f_{1}$$ 値に対する年齢別の預託実効線量換算係数を提供することである。この目的を達成するため、本研究では、$$f_{1}$$ 値を0から1の範囲で変化させて、1歳, 5歳および成人に対する預託実効線量換算係数を計算した。計算にはオークリッジ国立研究所の開発したDCALコードを利用した。この結果、吸収率が低くなると、他の年齢に比べて成人の換算係数が大きく減少することが分かった。これは、放射性セシウムが胃腸管で吸収された場合、その生物学的半減期は成人の方が長いため、1歳および5歳と比べて体内での被ばくが大きくなるためである。


Micro-PIXE analysis on adsorbent of extraction chromatography for MA(III) recovery

高畠 容子; 渡部 創; 小藤 博英; 竹内 正行; 野村 和則; 佐藤 隆博*

International Journal of PIXE, 26(3&4), p.73 - 83, 2017/09



Simulation study of personal dose equivalent for external exposure to radioactive cesium distributed in soil

佐藤 大樹; 古田 琢哉; 高橋 史明; Lee, C.*; Bolch, W. E.*

Journal of Nuclear Science and Technology, 54(9), p.1018 - 1027, 2017/09

福島第一原子力発電所事故で土壌に沈着した放射性セシウム($$^{134}$$Cs及び$$^{137}$$Cs)による外部被ばくに対する公衆の放射線安全性を確保するため、新生児, 1歳, 5歳, 10歳, 15歳及び成人が装着した個人線量計でモニタされる個人線量当量を、放射線輸送計算コードPHITSを用いて解析した。放射性セシウムは土壌中の特定の深さ(0.0, 0.5, 2.5, 5.0, 10.0及び50.0g/cm$$^2$$)に平板一様分布しているとし、各年齢の人体は精密人体数値模型により再現した。年齢別の個人線量当量の解析結果から、年齢が小さいほど個人線量当量の値が大きくなることが分かった。しかし、汚染環境中においても実用量である個人線量当量は防護量である実効線量をよく代表することと、地上100cm高さの周辺線量当量の値を超えないことが明らかになった。また、体積分布した線源に対する個人線量当量を導出する加重積分法により、福島で観測された指数分布線源による個人線量当量を解析したところ、解析値は福島で成人男性が装着した個人線量計により取得された実測値とよい一致を示した。


Current situations and discussions in Japan in relation to the new occupational equivalent dose limit for the lens of the eye

横山 須美*; 浜田 信行*; 林田 敏幸*; 辻村 憲雄; 立崎 英夫*; 黒澤 忠弘*; 青天目 州晶*; 大口 裕之*; 大野 和子*; 川浦 稚代*; et al.

Journal of Radiological Protection, 37(3), p.659 - 683, 2017/09


国際放射線防護委員会が2011年に水晶体の職業等価線量限度を下げることを勧告して以来、多くの議論が様々な国々でなされてきた。この論文は、日本における水晶体の放射線防護の現状と新しい水晶体線量限度の潜在的なインパクトに関する議論をとりまとめる。トピックは水晶体線量限度の歴史的変遷、水晶体の職業被ばくの現状(例えば、医療労働者, 原子力労働者、および福島原子力発電所労働者)と測定、生物学的研究および放射線白内障に関する疫学研究の現状を含んでいる。焦点は日本の状況に置かれているが、そのような情報の共有は他の多くの国々にとって有用になると思われる。


Magnetic properties of electron-doped LaCoO$$_3$$

富安 啓輔*; 佐藤 美嘉*; 小山 俊一*; 野島 勉*; 梶本 亮一; Ji, S.*; 岩佐 和晃*

Journal of the Physical Society of Japan, 86(9), p.094706_1 - 094706_6, 2017/09

We studied electron-doped LaCo$$_{1-y}$$Te$$^{6+}_{y}$$O$$_{3}$$ by magnetization measurements and neutron scattering. The effective Bohr magneton, estimated in the Curie-Weiss fitting around room temperature, is independent of $$y$$. This suggests that magnetic Co$$^{3+mathrm{(HS)}}$$, not nonmagnetic Co$$^{3+mathrm{(LS)}}$$, is mainly replaced by doped magnetic Co$$^{2+mathrm{(HS)}}$$. At the lowest temperatures, a Brillouin-function-like saturating behavior persists in the magnetization curves even in the high-$$y$$ samples, and neither clear magnetic reflection nor magnetic dispersion is observed by neutron scattering. These indicate that magnetic correlation is very weak in contrast to the well-known hole-doped LaCoO$$_3$$ accompanied with the transition to ferromagnetic metal. However, we also found that the low-$$y$$ samples exhibit nonnegligible enhancement in saturated magnetization by $$sim$$2 $$mu_B$$/doped-electron. All these characteristics are discussed in the light of activation and inactivation of spin-state blockade.


Work hardening, dislocation structure, and load partitioning in lath-martensite determined by ${it in situ}$ neutron diffraction line profile analysis

Harjo, S.; 川崎 卓郎; 友田 陽*; Gong, W.*; 相澤 一也; Tichy, G.*; Shi, Z.*; Ungar, T.*

Metallurgical and Materials Transactions A, 48(9), p.4080 - 4092, 2017/09

${it in situ}$ neutron diffraction during tensile deformation of lath martensite steel containing 0.22 mass% of carbon, is performed using TAKUMI of J-PARC. The diffraction peaks at plastically deformed states exhibit asymmetries as the reflection of redistributions of the stress and dislocation densities/arrangements in lath-packets where the dislocation glides are favorable (soft packet) and unfavorable (hard packet). The dislocation density is as high as 10$$^{15}$$ m$$^{-2}$$ at the as-quenched state, and then during tensile straining, the load and the dislocation density become different between the two lath-packets. The dislocation character and arrangement vary also in the hard packet, but hardly change in the soft packet. The hard packet plays an important role in the high work hardening in martensite, which could be understood by taking into account not only the increase of the dislocation density but also the change in dislocation arrangement.


JASMINE Version 3による溶融燃料-冷却材相互作用SERENA2実験解析

堀田 亮年*; 森田 彰伸*; 梶本 光廣*; 丸山 結

日本原子力学会和文論文誌, 16(3), p.139 - 152, 2017/09

Among twelve FCI cases conducted in the OECD/NEA/CSNI/SERENA2 test series using two facilities, six steam explosion cases, five from TROI and one from KROTOS, were analyzed by JASMINE V.3. Major model parameters were categorized into "focused zone", a core part of interest, and "peripheral zone", the initial and boundary conditions given intentionally for each test case. For the former, base values established through past validation studies of JASMINE V.3 were applied. The code was modified to implement the measured distribution of entrained droplet size acquired in TROI-VISU. For the latter, melt release histories were given as a combination of time tables of jet diameter and release velocity that were estimated based on image data and transit timing data of the melt leading edge. The base values were shown to predict impulse responses of SERENA2 systematically with a reasonable error band. A statistical analysis based on the LHS method was performed. Uncertainty ranges were given based on measurement errors and past validation studies in the JASMINE development. Underlying mechanisms causing apparent differences in the mechanical energy conversion ratio between two facilities were studied from the view point of breakup length and trigger timing.



岡島 智史; 若井 隆純

日本機械学会2017年度年次大会講演論文集(DVD-ROM), 5 Pages, 2017/09



機械工学分野における信頼性評価の導入と展開; 圧力設備の減肉評価に対する部分安全係数法の導入

岡島 智史

日本機械学会2017年度年次大会講演論文集(DVD-ROM), 3 Pages, 2017/09

減肉を受けた圧力設備の供用適性評価にあたって、検査等をはじめとする日常の保全活動に応じた安全係数を設定することが期待されており、そのためには検査結果および荷重のばらつきを考慮した信頼性評価を行うことが有効と考えられた。日本高圧力技術協会では、テクニカルレポートHPIS Z 109TR「信頼性に基づく圧力設備の減肉評価方法」を制定し、信頼性に基づく減肉評価の方法とその技術基盤を与えている。この評価方法の一つとして、部分安全係数法を用いた減肉評価方法を与えており、従来の経験的な安全係数を用いた手法と同等の簡便さで減肉評価を行うことを可能とした。本報では、HPIS Z 109TRに与えられた、部分安全係数法を用いた減肉評価方法について紹介する。


Electronic structure of ThRu$$_2$$Si$$_2$$ studied by angle-resolved photoelectron spectroscopy; Elucidating the contribution of U 5$$f$$ states in URu$$_{2}$$Si$$_{2}$$

藤森 伸一; 小畠 雅明; 竹田 幸治; 岡根 哲夫; 斎藤 祐児; 藤森 淳; 山上 浩志; 松本 裕司*; 山本 悦嗣; 立岩 尚之; et al.

Physical Review B, 96(12), p.125117_1 - 125117_9, 2017/09


The Fermi surface and band structure of $$mathrm{ThRu}_2mathrm{Si}_2$$ have been studied by angle resolved photoelectron spectroscopy (ARPES) with the incident photon energies of $$hnu$$ = 665-735 eV. Detailed band structure and the three-dimensional shape of the Fermi surface were derived experimentally, and they are quantitatively explained by the band-structure calculation based on the density functional approximation. Comparison of the experimental ARPES spectra of $$mathrm{ThRu}_2mathrm{Si}_2$$ with those of $$mathrm{URu}_2mathrm{Si}_2$$ shows that they have considerably different spectral profiles particularly in the energy range of $$E_mathrm{B} = E_mathrm{F}$$ - 1 eV. Some energy bands with their energy dispersions of about 1 eV observed in $$mathrm{URu}_2mathrm{Si}_2$$ are missing in the ARPES spectra of $$mathrm{ThRu}_2mathrm{Si}_2$$ measured along the same high symmetry line of Brillouin zone, suggesting that U 5$$f$$ states form these bands in $$mathrm{URu}_2mathrm{Si}_2$$. The relationship between the ARPES spectra of $$mathrm{URu}_2mathrm{Si}_2$$ and $$mathrm{ThRu}_2mathrm{Si}_2$$ is very different from the case between $$mathrm{CeRu}_2mathrm{Si}_2$$ and $$mathrm{LaRu}_2mathrm{Si}_2$$ where their intrinsic difference is limited only in the very vicinity of the Fermi energy. The present result argues that the U 5$$f$$ electrons in $$mathrm{URu}_2mathrm{Si}_2$$ have strong hybridization with ligand states, and essentially have an itinerant character.


Electronic structures of U$$X_3$$ ($$X$$=Al, Ga, and In) studied by photoelectron spectroscopy

藤森 伸一; 小畠 雅明; 竹田 幸治; 岡根 哲夫; 斎藤 祐児; 藤森 淳; 山上 浩志; 芳賀 芳範; 山本 悦嗣; 大貫 惇睦*

Physical Review B, 96(11), p.115126_1 - 115126_10, 2017/09

The electronic structures of U$$X_3$$ ($$X$$=Al, Ga, and In) were studied by photoelectron spectroscopy to understand the the relationship between their electronic structure and magnetic properties. The band structures and Fermi surfaces of UAl$$_3$$ and UGa$$_3$$ were revealed experimentally by angle-resolved photoelectron spectroscopy (ARPES), and they were compared with the result of band structure calculations. The topologies of the Fermi surfaces and the band structures of UAl$$_3$$ and UGa$$_3$$ were explained reasonably well by the calculation, although bands near the Fermi level ($$E_mathrm{F}$$) were renormalized owing to the finite electron correlation effect. The topologies of the Fermi surfaces of UAl$$_3$$ and UGa$$_3$$ are very similar to each other, except for some minor differences. Such minor differences in their Fermi surface or electron correlation effect might take an essential role in their magnetism.


Observation of momentum-dependent charge excitations in hole-doped cuprates using resonant inelastic X-ray scattering at the oxygen $$K$$ edge

石井 賢司*; 遠山 貴巳*; 浅野 駿*; 佐藤 研太朗*; 藤田 全基*; 脇本 秀一; 筒井 健二*; 曽田 繁利*; 宮脇 淳*; 丹羽 秀治*; et al.

Physical Review B, 96(11), p.115148_1 - 115148_8, 2017/09



We investigate electronic excitations in La$$_{2-x}$$(Br,Sr)$$_x$$CuO$$_4$$ using resonant inelastic X-ray scattering (RIXS) at the oxygen $$K$$ edge. We observed momentum-dependent spectral weight below 1 eV, which is consistent with theoretical calculation of the dynamical charge structure factor on oxygen orbitals in a three-band Hubbard model. Our results confirm that the momentum-dependent charge excitations exist on the order of the transfer energy ($$t$$), and the broad spectral line shape indicates damped and incoherent character of the charge excitations at the energy range in the doped Mott insulators.


Experimental study on outer surface cooling of containment vessel by using CIGMA

柴本 泰照; 石垣 将宏; 安部 諭; 与能本 泰介

Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 14 Pages, 2017/09

The present paper introduces the recent outcome from the CIGMA experiments regarding containment vessel cooling, in which an external side of a vessel upper head was flooded by water. The test vessel was initially pressurized by steam and noncondensable gas (air and/or helium), and was subsequently cooled by pouring water to the outside of the vessel top. Similar experiments were performed by authors using air-steam binary system in the previous study, which showed several characteristic phenomena such as inverse temperature stratification. The experimental conditions were extended systematically in this study to investigate the effects of initial gas composition and distribution in a vessel. The measurement results indicated that natural circulation was significantly affected by distributions of each gas species. In particular, it was enhanced when the gas density became heavier after condensation on the vessel inner wall, while it was suppressed when the gas density became lighter, creating density stratification with helium-rich gas in the upper region. The results are explained by the simplified model.


Experiments on gas entrainment phenomena due to free surface vortex induced by flow passing beside stagnation region

江連 俊樹; 伊藤 啓; 田中 正暁; 大島 宏之; 亀山 祐理*

Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 9 Pages, 2017/09



An Experimental study on the fragmentation and accompanying cooling behaviors of a simulated molten oxide fuel penetrating into a sodium pool

松場 賢一; 神山 健司; 豊岡 淳一; Zuev, V. A.*; Kolodeshnikov, A. A.*

Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) (USB Flash Drive), 11 Pages, 2017/09



Influence of the air/steam mixing ratio in atmosphere on zirconium cladding oxidation in spent fuel pool accident condition

根本 義之; 加治 芳行; 小川 千尋*; 中島 一雄*; 東條 匡志*

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09



Behavior of high-burnup advanced LWR fuels under design-basis accident conditions

天谷 政樹; 宇田川 豊; 成川 隆文; 三原 武; 谷口 良徳

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

JAEA has conducted a research program called ALPS-II program for advanced fuels of LWRs. In this program, the tests simulating a RIA and a LOCA have been performed on the high burnup advanced fuels irradiated in European commercial reactors. The failure limits of the high-burnup advanced fuels under RIA conditions have been obtained by the pulse irradiation tests at the NSRR in JAEA. The information about pellet fragmentation etc. during the pulse irradiations was also obtained from post-test examinations on the test rods after the pulse irradiation tests. As for the simulated LOCA test, integral thermal shock tests and high-temperature oxidation tests have been performed at the RFEF in JAEA. The fracture limits under LOCA and post-LOCA conditions etc. of the high-burnup advanced fuel cladding have been investigated, and it was found that in terms of these materials the fracture boundaries do not decrease and the oxidation does not significantly accelerate in the burnup level examined.


Development of experimental and analytical technologies for fission product chemistry under LWR severe accident condition

宮原 直哉; 三輪 周平; 中島 邦久; 逢坂 正彦

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 9 Pages, 2017/09



Fuel behavior analysis for accident tolerant fuel with sic cladding using adapted FEMAXI-7 code

白数 訓子; 齋藤 裕明; 山下 真一郎; 永瀬 文久

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 8 Pages, 2017/09



Technical basis of accident tolerant fuel updated under a Japanese R&D project

山下 真一郎; 永瀬 文久; 倉田 正輝; 野澤 貴史; 渡部 清一*; 桐村 一生*; 垣内 一雄*; 近藤 貴夫*; 坂本 寛*; 草ヶ谷 和幸*; et al.

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

我が国では、事故耐性燃料の技術基盤を整備するために2015年に軽水炉の事故耐性燃料等(ATFs)に関する研究開発プロジェクトが立ち上がった。日本原子力研究開発機構は、国内のプラントメーカ, 燃料メーカ, 大学等が有する国内軽水炉においてジルカロイを商用利用した際の経験、知識を最大限活用するために、これらの機関と協力して本プロジェクトを実施するとともに取りまとめを行っている。プロジェクトの中で検討されているATF候補材料は、微細な酸化物粒子を分散することで強化されたFeCrAl鋼(FeCrAl-ODS鋼)と炭化ケイ素(SiC)複合材料であり、通常運転時の燃料性能は同等かそれ以上で、事故時にはジルカロイよりも長い時間原子炉炉心においてシビアアクシデント条件に耐えることが期待されている。本論文では、日本のプロジェクトで実施中の研究開発の進捗について報告する。


Analytical study of the applicability of FeCrAl-ODS cladding for BWR

高野 渉*; 草ヶ谷 和幸*; 後藤 大輔*; 坂本 寛*; 山下 真一郎

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09



Improving the corrosion resistance of silicon carbide for fuel in BWR environments by using a metal coating

石橋 良*; 田邊 重忠*; 近藤 貴夫*; 山下 真一郎; 永瀬 文久

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09



Welding technology R&D of Japanese accident tolerant fuel claddings of FeCrAl-ODS steel for BWRS

木村 晃彦*; 湯澤 翔*; 坂本 寛*; 平井 睦*; 草ヶ谷 和幸*; 山下 真一郎

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09



The Applicability of SiC-SiC fuel cladding to conventional PWR power plant

古本 健一郎*; 渡部 清一*; 山本 晃久*; 手島 英行*; 山下 真一郎; 齋藤 裕明; 白数 訓子

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09



Overview of Japanese development of accident tolerant FeCrAl-ODS fuel claddings for BWRs

坂本 寛*; 平井 睦*; 鵜飼 重治*; 木村 晃彦*; 山路 哲史*; 草ヶ谷 和幸*; 近藤 貴夫*; 山下 真一郎

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 7 Pages, 2017/09



Safety evaluation of accident tolerant fuel with SiC/SiC cladding

佐藤 寿樹*; 武内 豊*; 垣内 一雄*; 山下 真一郎; 永瀬 文久

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 9 Pages, 2017/09



FEMAXI-7 prediction of the behavior of BWR-type accident tolerant fuel rod with FeCrAl-ODS steel cladding in normal condition

山路 哲史*; 山崎 大輝*; 岡田 知也*; 坂本 寛*; 山下 真一郎

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09



Effect of oxidizing metallic ions on corrosion of stainless steel during concentration process simulating High-level Activity Liquid Waste (HALW) concentrator

入澤 恵理子; 加藤 千明; 鴨志田 美智雄*; 袴塚 保之*; 上野 文義; 山本 正弘

Proceedings of European Corrosion Congress 2017 (EUROCORR 2017) and 20th ICC & Process Safety Congress 2017 (USB Flash Drive), 9 Pages, 2017/09

In the PUREX method for reprocessing of nuclear spent fuels, the HNO$$_{3}$$ media with high concentration is heated up to boiling point to dissolve fuels. The process solutions containing oxidizing metallic ions dissolved from spent fuels are very corrosive because of these high oxidizing activities, and the corrosion problem have appeared on the stainless steel concentrators and evaporators such as the intergranular corrosion of stainless steel. We focused how the change of solution composition and temperature on the corrosion rate of stainless steel under the operation condition of High-level Active Liquid West concentrator of reprocessing plant in Japan. The corrosion immersion tests and the electrochemical measurements were performed using R-SUS304ULC as stainless steel test samples and the HNO$$_{3}$$ solutions containing following oxidizing metallic ions. The corrosion rate increased caused by increasing of the HNO$$_{3}$$ and metallic ions concentration. The cathodic polarization curves showed that the current density increased with increasing of the concentration of HNO$$_{3}$$ and metallic ions. Moreover, the results showed that the contribution of Ru and V which can maintain the acceleration effect on the corrosion because of high re-oxidation rate after the reductant with the corrosion reaction in the solution.


Characterization study of four candidate technologies for nuclear material quantification in fuel debris at Fukushima Daiichi Nuclear Power Station, 4; Numerical simulations for active neutron technique

米田 政夫; 前田 亮; 大図 章; 呉田 昌俊; 藤 暢輔

Proceedings of International Nuclear Fuel Cycle Conference (GLOBAL 2017) (USB Flash Drive), 3 Pages, 2017/09

アクティブ中性子法の一つであるFNDI法を用いた核物質の計量管理技術の開発を行っている。FNDI法は、対象物にパルス中性子を照射し、そこで発生する核分裂中性子の総数及び消滅時間を用いて核分裂性物質量を求める測定法である。FNDI法を用いたデブリ計測システムの設計解析に取り組んでおり、次のような計算モデルを作成してシミュレーションを実施した。装置高さ: 140cm、装置外径: 80cm、He-3検出器(長さ100cm、直径2.5cm)本数: 16本。デブリの状態として湿式と乾式の2種類を考え、乾式デブリでは中性子の減速効果を補うために収納管周りにポリエチレンを取り付けている。シミュレーションは計算コードMVPを用いた。本発表では燃焼組成や均質度を変えた様々なデブリに対する計算結果及びFNDI法を用いたデブリ測定の適用範囲に関する検討結果を示す。


Hazard curve evaluation for forest fire smoke effects on air-cooling decay heat removal systems

岡野 靖; 山野 秀将

Proceedings of International Topical Meeting on Probabilistic Safety Assessment and Analysis 2017 (PSA 2017) (USB Flash Drive), p.1334 - 1342, 2017/09



Release behavior of Cs and its chemical form during late phase of Fukushima Daiichi Nuclear Power Plant accident

日高 昭秀; 横山 裕也

Proceedings of Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2017 (AWC 2017) (USB Flash Drive), p.29 - 42, 2017/09

福島第一原子力発電所事故後期に東海村で測定された空気中のCsの性状が3月30日にガス状から粒子状に変わったことに関し、B$$_{4}$$C制御材を用いたPhebus FPT3実験やWSPEEDIコードによるソースターム逆算の結果を参照して、CsOHがB$$_{4}$$C起源のH$$_{3}$$BO$$_{3}$$と反応して生成するCsBO$$_{2}$$が再蒸発したことが原因であること、また、CsBO$$_{2}$$は環境中に放出後、逆反応を起こし、H$$_{3}$$BO$$_{3}$$が水に溶けたことがBの測定を難しくしているとの仮説を提案した。本仮説に基づく計算は、3月20日以降の炉心冷却注水量の最適化に伴う温度上昇時の環境中への放出量増大と合わせ、放出挙動を的確に再現できたが、推論の実証が重要である。今後は、様々な測定データを詳細に分析し、Bの存在を確認することが重要と考える。


Beam-based compensation of extracted-beam displacement caused by field ringing of pulsed kicker magnets in the 3 GeV rapid cycling synchrotron of the Japan Proton Accelerator Research Complex

原田 寛之; Saha, P. K.; 田村 文彦; 明午 伸一郎; 發知 英明; 林 直樹; 金正 倫計; 長谷川 和男

Progress of Theoretical and Experimental Physics (Internet), 2017(9), p.093G01_1 - 093G01_16, 2017/09


J-PARC 3GeVシンクロトロン(RCS)は、設計出力1MWの大強度陽子加速器である。このRCSで3GeVまで加速された陽子ビームは、リング内の8台のパルスキッカー電磁石で取り出しラインへ導き、物質生命科学実験施設や後段の加速器へ供給されている。しかしながら、この電磁石の電磁回路的なリンギングにより時間的な磁場変調を生じており、取り出しビームが大きく変動していた。この変動は、中性子源標的の故障リスクの増大や後段加速器のビーム損失の増大を生じ、大きな課題である。特別な短パルスビームと各電磁石のタイミングスキャンを行い、取り出しビームの位置変動を測定することで、この磁場変調を実測し把握した。それを用いて各電磁石の磁場変調を抑制する最適なタイミングを求め、適用することで装置の改造を行うことなく要求以上の精度のビーム取り出しを実現した。さらにタイミングのずれを自動で測定し補正するシステムを導入し、安定化も実現した。この論文では、手法や成果を報告する。


Materials and Life Science Experimental Facility at the Japan Proton Accelerator Research Complex, 1; Pulsed spallation neutron source

高田 弘; 羽賀 勝洋; 勅使河原 誠; 麻生 智一; 明午 伸一郎; 粉川 広行; 直江 崇; 涌井 隆; 大井 元貴; 原田 正英; et al.

Quantum Beam Science (Internet), 1(2), p.8_1 - 8_26, 2017/09




杉浦 広幸*; 酒井 創*; 佐藤 志彦; 末木 啓介*

Radioisotopes, 66(9), p.311 - 319, 2017/09



Atomic-scale visualization of surface-assisted orbital order

Kim, H.*; 吉田 靖雄*; Lee, C.-C.*; Chang, T.-R.*; Jeng, H.-T.*; Lin, H.*; 芳賀 芳範; Fisk, Z.*; 長谷川 幸雄*

Science Advances (Internet), 3(9), p.eeao0362_1 - eeao0362_5, 2017/09

We report a first, real-space, imaging of an orbital ordered structure on a cobalt-terminated surface of the well-studied heavy fermion compound CeCoIn$$_5$$. Within small tip-sample distances, the cobalt atoms on a cleaved (001) surface take on dumbbell shapes alternatingly aligned in the [100] and [010] directions in scanning tunneling microscopy topographies. First-principles calculations reveal that this staggered orbital order is triggered by enhanced on-site Coulomb interaction at the surface.


Scaling of memories and crossover in glassy magnets

Samarakoon, A. M.*; 高橋 満*; Zhang, D.*; Yang, J.*; 片山 尚幸*; Sinclair, R.*; Zhou, H. D.*; Diallo, S. O.*; Ehlers, G.*; Tennant, D. A.*; et al.

Scientific Reports (Internet), 7(1), p.12053_1 - 12053_8, 2017/09



Glassiness is ubiquitous and diverse in characteristics in nature. Understanding their differences and classification remains a major scientific challenge. Here, we show that scaling of magnetic memories with time can be used to classify magnetic glassy materials into two distinct classes. The systems studied are high temperature superconductor-related materials, spin-orbit Mott insulators, frustrated magnets, and dilute magnetic alloys. Our bulk magnetization measurements reveal that most densely populated magnets exhibit similar memory behavior characterized by a relaxation exponent of $$1-n$$ $$approx$$ $$0.6$$(1). This exponent is different from $$1-n$$ $$approx$$ $$1/3$$ of dilute magnetic alloys that was ascribed to their hierarchical and fractal energy landscape, and is also different from $$1-n=1$$ of the conventional Debye relaxation expected for a spin solid, a state with long range order.



青柳 和平; 石井 英一

資源・素材講演集(インターネット), 4(2), 7 Pages, 2017/09

高レベル放射性廃棄物の地層処分において、処分坑道等の地下施設の掘削による応力再配分の影響により、坑道壁面周辺岩盤の水理・力学特性が顕著に変化する領域が生じる。このような領域を掘削損傷領域(Excavation Damaged Zone: EDZ)と呼ぶ。幌延深地層研究センターの350m調査坑道では、堆積軟岩である珪質泥岩を対象として、ボアホール・テレビューア観察、コア観察および透水試験を行い、坑道周辺のEDZの水理・力学特性を調査している。試験結果から、坑道掘削に起因して生じた引張割れ目の発達と透水係数の増大が認められたことから、坑道から0.2$$sim$$1.0mの範囲にEDZが発生したと推定した。これを理論的に検証するために、二次元の水理・力学連成解析を実施した。解析では、坑道掘削直後は掘削解放面を非排水条件、支保工設置後は排水条件とした。この結果、壁面から0.6$$sim$$1.4mの範囲まで引張破壊が生じる結果となり、原位置で観測されたEDZの範囲と概ね整合する結果が得られた。また、坑道掘削時の非排水挙動に伴う有効応力の低下が、原位置で確認された引張割れ目の形成や発達に寄与していることが示された。以上のことから、連成解析により、原位置のEDZの発生メカニズムを把握することができた。


Operation status of the J-PARC RF-driven H$$^{-}$$ ion source

小栗 英知; 大越 清紀; 池上 清*; 高木 昭*; 浅野 博之; 柴田 崇統*; 南茂 今朝雄*; 上野 彰; 神藤 勝啓

AIP Conference Proceedings 1869, p.030053_1 - 030053_7, 2017/08



High density plasma calculation of J-PARC RF negative ion source

柴田 崇統*; 浅野 博之; 池上 清*; 内藤 富士雄*; 南茂 今朝雄*; 小栗 英知; 大越 清紀; 神藤 勝啓; 高木 昭*; 上野 彰

AIP Conference Proceedings 1869, p.030017_1 - 030017_11, 2017/08

J-PARCでは2014年9月より、セシウム(Cs)添加型・マルチカスプ・高周波放電型(RF)負水素(H$$^{-}$$)イオン源の利用運転が開始され、電流値45mA、繰返し1.25%(0.5ms, 25Hz)のH-ビームを1000時間連続で引き出すことに成功している。本研究では、J-PARCイオン源内のRFプラズマに対する数値計算モデルを構築することで、プラズマの点火過程と定常状態におけるH$$^{-}$$生成・輸送に関わる物理過程を解明する。シミュレーションモデルでは、(1)荷電粒子(電子,水素陽イオン, Csイオン)、(2)イオン源内に形成される誘導性・容量性電磁場の時間変化、および(3)荷電粒子と水素原子・分子間の衝突過程を同時に計算する。また、同モデルを高エネルギー加速器研究機構並列計算機システムA(32ノード・256GBメモリ)に適用することで、10$$^{18}$$m$$^{-3}$$以上の高密度となるRFプラズマの挙動を十分な統計性を以て計算することが可能である。発表では、RFプラズマの成長過程に重要なプラズマパラメータを、プラズマ温度・密度、および電磁場分布の時間発展とともに示す。


Thermal-hydraulic analyses of the High-Temperature engineering Test Reactor for loss of forced cooling at 30% reactor power

高松 邦吉

Annals of Nuclear Energy, 106, p.71 - 83, 2017/08



Quantum optimal control of the isotope-selective rovibrational excitation of diatomic molecules

黒崎 譲*; 横山 啓一

Chemical Physics, 493, p.183 - 193, 2017/08


塩化リチウム分子の同位体選択的振動回転励起の最適パルス波形を求めた。振動回転が基底準位にあるLiCl-35とLiCl-37の混合分子集団にレーザーパルスを照射し、LiCl-35($$nu$$=0, $$J$$=0)とLiCl-37($$nu$$=1, $$J$$=1)を生成する最適波形を最適制御理論により計算した。その結果、回転遷移だけを利用する方が効率よく選択励起を起こすことができることが示された。


Performance degradation of candidate accident-tolerant cladding under corrosive environment

永瀬 文久; 坂本 寛*; 山下 真一郎

Corrosion Reviews, 35(3), p.129 - 140, 2017/08



Effective removal of selenite and selenate ions from aqueous solution by barite

徳永 紘平*; 高橋 嘉夫*

Environmental Science & Technology, 51(16), p.9194 - 9201, 2017/08


バライト(重晶石, BaSO$$_{4}$$)は、溶解度が低く、安定性が非常に高い鉱物であり、周囲の環境が変化しても元素を保持し続けるため、有害元素を安定に隔離する鉱物として非常に有用である。本論文では、対象元素として、高い毒性を持ち、選択的な除去が難しく、有効な処理処分技術が乏しいセレンのオキソアニオン(セレン酸: SeO$$_{4}$$$$^{2-}$$,亜セレン酸: SeO$$_{3}$$$$^{2-}$$)に対して実験を行い、これらの元素の共沈過程を分子レベルで明らかにすることで、溶液中からこれらの元素を効率的に除去するための条件を最適化した。実験の結果、バライトへの亜セレン酸の分配には、鉱物表面への微量元素の吸着のしやすさ(=1化学的な親和性)と鉱物構造内での安定性(=2構造規制)の2つが、またセレン酸の分配には構造規制のみがそれぞれ強く働くことが示され、これらの条件を調整することで溶液からの80%以上の除去がセレン酸、亜セレン酸ともに達成された。



飯塚 理子*; 八木 健彦*; 後藤 弘匡*; 奥地 拓生*; 服部 高典; 佐野 亜沙美

波紋, 27(3), p.104 - 108, 2017/08



Estimation of the vertical distribution of radiocesium in soil on the basis of the characteristics of $$gamma$$-ray spectra obtained via aerial radiation monitoring using an unmanned helicopter

越智 康太郎; 佐々木 美雪; 石田 睦司*; 濱本 昌一郎*; 西村 拓*; 眞田 幸尚

International Journal of Environmental Research and Public Health, 14(8), p.926_1 - 926_14, 2017/08




佐藤 達彦

Isotope News, (752), p.50 - 53, 2017/08

原子放射線の影響に関する国連科学委員会(UNSCEAR)が2008年に発表したレポートでは、公衆の宇宙線被ばく線量の世界平均値は年間0.38mSvであり、全自然放射線による被ばく線量の約16%を占めると結論づけている。しかし、この値は限られた実測から単純な仮定に基づいて推定した概算値であり、宇宙線強度の高度・緯度・経度に対する複雑な依存性や詳細な人口分布を考慮して評価した値ではない。そこで我々の研究グループでは、独自に開発した宇宙線強度計算モデルと様々なデータベースを組み合わせ、公衆の宇宙線被ばく線量の人口平均値や分散を世界230ヶ国 に対して詳細に評価し、その世界平均値を導出した。本稿では、宇宙線被ばくの概要を解説するとともに、その評価手法や評価結果を簡単に紹介する。



青柳 和平; 名合 牧人*

地盤工学会誌, 65(8), p.12 - 15, 2017/08



Uplift and denudation history of the Akaishi Range, a thrust block formed by arc-arc collision in central Japan; Insights from low-temperature thermochronometry and thermokinematic modeling

末岡 茂; 池田 安隆*; 狩野 謙一*; 堤 浩之*; 田上 高広*; Kohn, B. P.*; 長谷部 徳子*; 田村 明弘*; 荒井 章司*; 柴田 健二*

Journal of Geophysical Research; Solid Earth, 122(8), p.6787 - 6810, 2017/08



Thermodynamic study of gaseous CsBO$$_{2}$$ by Knudsen effusion mass spectrometry

中島 邦久; 高井 俊秀; 古川 智弘; 逢坂 正彦

Journal of Nuclear Materials, 491, p.183 - 189, 2017/08

軽水炉のシビアアクシデント時、ボロンの影響を考慮した熱力学平衡計算によれば、燃料から放出されるCsの気相中での主な化学形の一つとして、CsBO$$_{2}$$(g)が生成すると予想されている。しかし、核燃料や核分裂生成物などの熱力学データを収めた編纂物によれば、これまで報告されているCsBO$$_{2}$$の蒸気圧データの不確かさのために、この解析に使用されたCsBO$$_{2}$$(g)の熱力学データの信頼性は乏しいと評価されている。そのため、信頼性の高いCsBO$$_{2}$$(g)の熱力学データを得ることを目的に、高温質量分析法によるCsBO$$_{2}$$の平衡蒸気圧測定を試みた。その結果、CsBO$$_{2}$$の平衡蒸気圧測定データを用いて、第二法則,第三法則処理により評価した気体CsBO$$_{2}$$の標準生成エンタルピー$$Delta$$$$_{f}$$H$$^{circ}$$$$_{298}$$(CsBO$$_{2}$$,g)は、それぞれ、-700.7$$pm$$10.7kJ/mol, -697.0$$pm$$10.6kJ/molとなり、過去に報告されている蒸気圧データを用いて得られた第二法則,第三法則処理による$$Delta$$$$_{f}$$H$$^{circ}$$$$_{298}$$(CsBO$$_{2}$$,g)の差異よりも小さくなったことから、これまでよりも信頼性の高い熱力学データを取得できたことが分かった。さらに、既存の$$Delta$$$$_{f}$$H$$^{circ}$$$$_{298}$$(CsBO$$_{2}$$,g)についても、本研究で得られた$$Delta$$$$_{f}$$H$$^{circ}$$$$_{298}$$(CsBO$$_{2}$$,g)の値と誤差の範囲で一致したことから、信頼性が高いことが分かった。


Examination of $$^{131}$$I and $$^{137}$$Cs releases during late phase of Fukushima Daiichi NPP accident by using $$^{131}$$I/$$^{137}$$Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

日高 昭秀; 横山 裕也

Journal of Nuclear Science and Technology, 54(8), p.819 - 829, 2017/08




Corrigendum; Examination of $$^{131}$$I and $$^{137}$$Cs releases during late phase of Fukushima Daiichi NPP accident by using $$^{131}$$I/$$^{137}$$Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data, J. Nucl. Sci. Technol. 2017, Corrected vertical axis of Figure 6

日高 昭秀; 横山 裕也

Journal of Nuclear Science and Technology, 54(8), P. i, 2017/08

以前に発表した論文(Examination of $$^{131}$$I and $$^{137}$$Cs releases during late phase of Fukushima Daiichi NPP accident by using $$^{131}$$I/$$^{137}$$Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data [Journal of Nuclear Science and Technology, vol.54(8), pp.819-829 (2017)])における図6の縦軸の訂正である。


Hydrogen production by $$gamma$$-ray irradiation from different types of zeolites in aqueous solution

熊谷 友多; 木村 敦*; 田口 光正*; 渡邉 雅之

Journal of Physical Chemistry C, 121(34), p.18525 - 18533, 2017/08



Experimental study on the deformation and failure of the bellows structure beyond the designed internal pressure

安藤 勝訓; 矢田 浩基; 月森 和之; 一宮 正和*; 安濃田 良成*

Journal of Pressure Vessel Technology, 139(6), p.061201_1 - 061201_12, 2017/08




上澤 伸一郎; 吉田 啓之

混相流シンポジウム2017講演論文集(USB Flash Drive), 2 Pages, 2017/08




山口 正剛

まてりあ, 56(8), p.480 - 483, 2017/08



Unusual plastic deformation behavior in lath martensitic steel containing high dislocation density

Harjo, S.; 川崎 卓郎; 友田 陽*; Gong, W.

Materials Science Forum, 905, p.46 - 51, 2017/08

To understand the strengthening mechanism of a metallic material with high dislocation density, the plastic deformation behavior of lath martensite was studied by means of in situ neutron diffraction measurements during tensile deformations using a 22SiMn2TiB steel and a Fe-18Ni alloy. The characteristics of dislocation were analyzed and were discussed with the relation of stress-strain curves. The dislocation densities induced by martensitic transformation during heat-treatment in both materials were found to be originally as high as 10$$^{15}$$ m$$^{-2}$$ order, and subsequently to increase slightly by the tensile deformation. The parameter M value which displays the dislocation arrangement dropped drastically at the beginning of plastic deformation in both materials, indicating that the random arrangement became more like a dipole arrangement.


Quantitative evaluation of texture and dislocations during annealing after hot deformation in austenitic steel using neutron diffraction

友田 陽*; 佐藤 成男*; Uchida, M.*; 徐 平光; Harjo, S.; Gong, W.; 川崎 卓郎

Materials Science Forum, 905, p.25 - 30, 2017/08

Microstructural change during hot compressive deformation at 700 $$^{circ}$$C followed by isothermal annealing for a Fe-32Ni austnitic alloy was monitored using ${it in situ}$ neutron diffraction. The evolution of deformation texture with 40% compression and its change to recrystallization texture during isothermal annealing were presented by inverse pole figures for the axial and radial directions. The change in dislocation density was tracked using the convolutional muli-profile whole profile fitting method. To obtain the fitting results with good statistics, at least 60 s time-slicing for the event-mode recorded data was needed. The average dislocation density in 60 s after hot compression was determined to be 2.8 $$times$$ 10$$^{14}$$ m$$^{-2}$$ that decreased with increasing of annealing time.


Structure of the magnetic excitations in the spin-1/2 triangular-lattice Heisenberg antiferromagnet Ba$$_{3}$$CoSb$$_{2}$$O$$_{9}$$

伊藤 沙也*; 栗田 伸之*; 田中 秀数*; 河村 聖子; 中島 健次; 伊藤 晋一*; 桑原 慶太郎*; 加倉井 和久*

Nature Communications, 8, p.235_1 - 235_6, 2017/08


A spin-1/2 triangular-lattice Heisenberg antiferromagnet (TLHAF) is a prototypical frustrated quantum magnet, which exhibits remarkable quantum many-body effects that arise from the synergy between spin frustration and quantum fluctuation. The ground-state properties of a spin-1/2 TLHAF are theoretically well understood. However, magnetic excitations are less well understood and the theoretical consensus is limited. The experimental study of the magnetic excitations in spin-1/2 TLHAFs has also been limited. Here we show the whole picture of magnetic excitations in the spin-1/2 TLHAF Ba$$_{3}$$CoSb$$_{2}$$O$$_{9}$$ investigated by inelastic neutron scattering. Significantly different from the theory, the excitation spectra have a three-stage energy structure. The lowest first stage is composed of dispersion branches of single-magnon excitations. The second and third stages are dispersive continua accompanied by columnar continuum extending above 10 meV, which is six times larger than the exchange interaction J=1.67 meV. Our results indicate the necessity of a new theoretical framework.


1F事故による環境回復に伴う廃棄物の管理と除去土壌の減容・再生利用の取り組み,5; 低レベル放射性廃棄物の処分費用の積算

仲田 久和; 坂井 章浩; 天澤 弘也; 坂本 義昭

日本原子力学会誌, 59(8), p.447 - 449, 2017/08


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