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1
Thermodynamic equilibrium constants for important isosaccharinate reactions; A Review
Rai, D.*; Kitamura, Akira
Journal of Chemical Thermodynamics, 114, p.135 - 143, 2017/11
Isosaccharinic acid is a cellulose degradation product that can form in low-level nuclear waste repositories and is known to form strong complexes with many elements, including actinides, disposed of in these repositories. We (1) reviewed the available data for deprotonation and lactonisation constants of isosaccharinic acid, and the isosaccharinate binding constants for Ca, Fe(III), Th, U(IV), U(VI), Np(IV), Pu(IV), and Am(III), (2) summarized complexation constant values for predicting actinide behavior in geologic repositories in the presence of isosaccharinate, and (3) outlined additional studies to acquire reliable thermodynamic data where the available data are inadequate.
2
Clearance of concrete generated from modification activities of JRR-3; Results for measuring and evaluating radioactivity concentration
Ogoshi, Yurie; Satoyama, Tomonori; Kishimoto, Katsumi; Nanri, Tomohiro; Suzuki, Takeshi; Tomioka, Osamu; Takaizumi, Hirohide*; Kanno, Tomoyuki*; Maruyama, Tatsuya*
JAEA-Technology 2017-017, 152 Pages, 2017/08
At Nuclear Science Research Institute, clearance works for about 4,000 tons of extremely low-level radioactive concrete debris, which were generated from the modification activities of JRR-3 from FY 1985 to FY 1989 and stored in the waste storage facility NL, carried out. First of this clearance works, method for measuring and evaluating radioactivity concentration was approved by Minister of MEXT on July 25, 2008. And then, clearance works were started from FY 2009. Measuring and evaluating radioactivity concentration was achieved by using the approved method, and was confirmed by government. And then, clearance works were completed in FY 2014. The clearance concrete was recycled as a material for restoration works of the 2011 off the Pacific coast of Tohoku Earthquake. This report summarizes the results of measuring and evaluating radioactivity concentration, achievement of confirmation by government, recycling of cleared concrete and cost for clearance works.
3
Development of the observational construction technology in the Horonobe Underground Research Laboratory
Aoyagi, Kazuhei; Nago, Makito*
Jiban Kogakkai-Shi, 65(8), p.12 - 15, 2017/08
In this paper, we described the development of the supporting tool of observational construction of the underground research laboratory, and the monitoring result of hydro-mechanical properties around the gallery wall. As an observational construction tool, we developed a "3D geological structure/construction data visualization system". The geological data, measurement data, construction data, and prediction analysis results are visualized and integrated comprehensively as the construction proceeds. The planned support pattern was examined according to the visualized data. In addition, the Excavation Damaged Zone (EDZ) was extended within 1.0 m from the gallery wall. In this area, hydraulic conductivity was enhanced. However, the extent of the EDZ was not enlarged along with time; the stability of the support was also confirmed on the basis of the measurement of stress in the shotcrete. Integrating these results the observational construction considering the development of an EDZ can be established. This technology will have an important role in geological disposal of high-level radioactive waste.
4
Replacement of the glove port equipped with glove box in Nuclear Fuel Reprocessing Facility
Horigome, Kazushi; Taguchi, Shigeo; Nishida, Naoki; Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko
Nippon Hozen Gakkai Dai-14-Kai Gakujutsu Koenkai Yoshishu, p.381 - 384, 2017/08
東海再処理施設では、プルトニウム等の核燃料物質を安全に取り扱うため、閉じ込め機能(負圧)を有するグローブボックス(GB)が設置されており、各GBには、グローブを取り付けるためのグローブポート(ベークライト製)が取り付けられている。グローブポートには、グローブをグローブポートに直接取り付けるタイプと、インナーリングと呼ばれる塩ビ製の環に取り付けたグローブをグローブポートに挿入して取り付けるタイプ(以下、押し込み式グローブポート)の2種類が使われている。平成28年4月に、押し込み式グローブポートの1基に2ヵ所の割れが東海再処理施設において初めて確認された。なお、割れによるGB内の負圧の異常や、GB外への放射性物質の漏えいは確認されなかった。グローブポートは、ポートとポート押さえでパネルを挟み込む形で、ポートとポート押さえをネジで固定することによりGBパネルに取り付けられている。このため、固定ネジを取外すことでグローブポートは取り外しが可能な構造ではあるが、グローブポートをそのまま取外した場合、閉じ込め機能が破れ、GB内の放射性物質を拡散させる恐れがあるため、拡散防止措置を講じた上で、グローブポートの交換を実施する必要があった。そこで今回、GB内部の汚染をコントロールしながらグローブポートを更新する手法を確立した。本発表では、その交換手法について報告する。
5
Design and application of greenhouse on the maintenance of analytical machineries in Tokai Reprocessing Plant
Suzuki, Yoshimasa; Tanaka, Naoki; Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko
Nippon Hozen Gakkai Dai-14-Kai Gakujutsu Koenkai Yoshishu, p.385 - 389, 2017/08
Greenhouse is used in order to prevent diffusion of radioactive materials on the maintenance of machineries and decomposition of the analytical equipment such as glove box in Tokai Reprocessing Plant (TRP). The specifications of the greenhouse change depending on a risk of the radiation exposure, operation and environment. Design and application of original greenhouses in the analytical laboratory of TRP is summarized.
6
Consideration of methodology for estimating hydrochemistry based on results of resistivity logging in deep boreholes
Mizuno, Takashi; Iwatsuki, Teruki; Matsuzaki, Tatsuji*
Oyo Chishitsu, 58(3), p.178 - 187, 2017/08
本研究では、北海道幌延地域に分布する新第三系堆積岩を対象に、ボーリング孔において実施される比抵抗検層結果から間隙水の水質を定量的に把握するための手法について検討を行った。比抵抗検層結果からの水質の推定については、Archieの式等を用いて等価NaCl濃度を算出した。この等価NaCl濃度と、ボーリングコアから抽出した間隙水中のNaCl濃度の分析値をt検定により比較した結果、対象としたボーリング孔11孔のうち7孔において有意差(有意水準5%)がないと判断できた。分析値と計算値が一致しなかったボーリング孔については、塩分濃度が低いためにArchieの式が適用できないことや、ボーリング孔掘削時の掘削水が孔壁から混入したことによる水質の変化が原因と考えられた。これらを踏まえ、一定の条件を満たせば比抵抗検層結果から間隙水のNaCl濃度が定量的に推定可能であることを示すとともに、実際の調査現場において必要となる手順を整理した。
7
Preparation of uranium and plutonium mixed spike optimized for MOX analysis by isotope dilution mass spectrometry
Horigome, Kazushi; Taguchi, Shigeo; Yamamoto, Masahiko; Kuno, Takehiko; Surugaya, Naoki
JAEA-Technology 2017-016, 20 Pages, 2017/07
Mixed spikes of uranium and plutonium have been prepared for the determination of uranium and plutonium in dissolved MOX solution by isotope dilution mass spectrometry. Enriched uranium metal NBL CRM116 and plutonium metal NBL CRM126 were accurately weighed and then dissolved in nitric acid, respectively. Their dissolved solutions were mixed in a mass ratio of 1 to 2. The preparation values of uranium and plutonium were 1.0530 $$pm$$ 0.0008 mg/g (k=2) of uranium with a $$^{235}$$U relative mass fraction of 93.114 wt% and 2.0046 $$pm$$ 0.0019 mg/g (k=2) of plutonium with a $$^{239}$$Pu relative mass fraction of 97.934 wt%, respectively. The concentrations of uranium and plutonium in spike were confirmed by reverse isotope dilution mass spectrometry using tracer of $$^{233}$$U and $$^{242}$$Pu. Finally, the prepared spike was validated by parallel analysis of simulated sample of dissolved MOX solution. This spike was applied to measure the uranium and plutonium amount content of dissolved MOX solutions using isotope dilution mass spectrometry.
8
Diffusion experiment using block sample of the Toki granite
Hama, Katsuhiro; Iwasaki, Riyo*; Morikawa, Keita*
JAEA-Technology 2017-015, 45 Pages, 2017/07
Tono Geoscience Center of Japan Atomic Energy Agency has been carrying out the Mizunami Underground Research Laboratory Project. The goal of mass transport study is to obtain a better understanding of mass transport phenomena in the geological environment as well as to develop technologies for measurement of the mass transport parameters, model construction, numerical analysis and validation of those technologies. This experiment was planned to understand the influence of the microscopic structure in the rock mass on the mass transport property. The diffusion experiment using rock sample was carried out. The macroscopic and microscopic observations were carried out to understand the distribution of tracer (uranine) after the diffusion experiment. The uranine was observed in the plagioclase, in the grain boundary and in the microfracture in the mineral grains. These results suggested that distribution of mineral and of microfracture could affect the diffusion property of uranine.
9
Rapid measurement of the chloride diffusion coefficient in concrete from combination of non-steady-state migration experiment and EPMA
Ogino, Masataka*; Owaki, Eiji*; Shirase, Mitsuyasu*; Nakayama, Masashi
Konkurito Kogaku Nenji Rombunshu (DVD-ROM), 39(1), p.703 - 708, 2017/07
塩化物イオンの拡散係数はコンクリートの耐久性を評価する重要な指標であるが、耐久性の高いコンクリートは物質透過抵抗性に優れるため、測定に時間を要する。著者らは非定常の電気泳動操作にEPMAを組み合わせた迅速法について検討した。浸入した塩化物イオンについて、浸入範囲と濃度分布を求め、塩化物イオンの分布から電気泳動が主たる輸送機構ではないと判断される浸入範囲を除外し、Nernst-Planckの式により拡散係数を求めた。この拡散係数は、塩水浸せき試験により得られる値とほぼ同等である。従来の試験と比較し、試験期間を1$$sim$$2割程度に短縮できる可能性があることが確認できた。
10
Application of controlled-potential coulometry as a primary method for the characterization of plutonium nitrate solutions being used for reference materials (Joint Research)
Yamamoto, Masahiko; Holland, M. K.*; Cordaro, J. V.*; Kuno, Takehiko; Surugaya, Naoki
JAEA-Technology 2017-014, 63 Pages, 2017/06
In this study, the controlled-potential coulometry has been applied as a primary method for characterizing the Pu master solutions being used as alternative source material for IDMS spikes. The coulometry system compliance with ISO12183 has been used for measurement. It has been calibrated using equipment traceable to the SI units. Plutonium standard samples have been measured to confirm the accuracy. The relative standard deviation is below 0.05%. The results agree with the reference value within $$pm$$0.05%. It is found that the Pu can be precisely analyzed by the coulometry system. Then, the Pu nitrate solution, which has been purified from mixed oxide powder containing relatively high $$^{239}$$Pu, has been measured. The relative standard deviation is below 0.05%. The relative expanded uncertainty is less than 0.074% at the 95% confidence interval (k=2). It is indicated that coulometric assay of Pu is fit for the purpose of characterizing reference materials.
11
Backfilling test in drilling pits as part of Groundwater REcovery Experiment in Tunnel (GREET) Project
Takayasu, Kentaro; Onuki, Kenji*; Kawamoto, Koji*; Takayama, Yusuke; Mikake, Shinichiro; Sato, Toshinori; Onoe, Hironori; Takeuchi, Ryuji
JAEA-Technology 2017-011, 61 Pages, 2017/06
The Groundwater REcovery Experiment in Tunnel (GREET) was put into effect as development of drift backfilling technologies. This test was conducted by making the Closure Test Drift (CTD) recovered with water after carrying out a plug around 40m distance from northern edge face of horizontal tunnel of depth 500m, for the purpose of investigation of recovering process of rock mass and groundwater under the influence of excavation of tunnel. This report presents the efforts of backfilling investigation using bentonite composite soil and execution of backfilling into borehole pits excavated in the CTD which were carried out in fiscal 2014 as a part of GREET, and succeeding observation results inside pits from September 2014 to March 2016.
12
Study on the evaluation method to determine the radioactivity concentration in radioactive waste generated from post-irradiation examination facilities, 2
Tsuji, Tomoyuki; Hoshino, Yuzuru; Sakai, Akihiro; Sakamoto, Yoshiaki; Suzuki, Yasuo*; Machida, Hiroshi*
JAEA-Technology 2017-010, 75 Pages, 2017/06
It is necessary for reasonable disposal to be studied on evaluation methods to determine radioactivity concentrations in the radioactive wastes, which is generated from post-irradiation examination (PIE) facilities, for establishment of reasonable confirmation methods concerning radioactive wastes generated from research, industrial, and medical facilities. It has been chosen the PIE facilities of NUCLEAR DEVELOPMENT CORPORATION as a model for this study. As a result, it has been confirmed that the theoretical methods are applied for the important nuclides (H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, Cs-137, Eu-154, U-234, U-235, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Am-241 and Cm-244).
13
Gas-strip methods of dissolved inorganic carbon in groundwater for radiocarbon analysis
Kato, Toshihiro; Iwatsuki, Teruki; Nishio, Tomohiro*
JAEA-Technology 2017-009, 30 Pages, 2017/06
Groundwater age is an important information to infer the groundwater flow. The radiocarbon ($$^{14}$$C) dating of the groundwater is primary method for the evaluation of groundwater flow. The carbon in the groundwater generally exist as a dissolved inorganic carbon (DIC). Though DIC in groundwater samples is usually collected by chemical precipitation method, the method requires lots of preparation to sample the carbon. Furthermore there are problems with the reproducibility on precipitation and measurement value. This study newly examined the application of gas-strip method to collect DIC in groundwater sample by using JAEA-made gas-strip system. The performance of the CO$$_{2}$$ gas-stripping from groundwater and the influence of sulfide are investigated. Based on these results, the operation procedures of gas-strip system and preparation method for the groundwater samples were summarized in this report.
14
Horonobe Underground Research Laboratory Project; Investigation program for the 2017 fiscal year
Hanamuro, Takahiro
JAEA-Review 2017-013, 22 Pages, 2017/06
As part of the research and development program on geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency (JAEA), is implementing the Horonobe Underground Research Laboratory Project (Horonobe URL Project) with the aim at investigating sedimentary rock formations. According to the research plan described in the 3rd Mid- and Long-term Plan of JAEA, according to the Horonobe URL Project, "Near-field performance study", "Demonstration of repository design option", and "Verification of crustal-movement buffering capacity of sedimentary rocks" are the top priority issues, and schedule for finishing the project and backfill plan will be decides by the end of 2019 Fiscal Year. The Horonobe URL Project is planned to extend over a period of about 20 years. This report summarizes the investigation program for the 2017 fiscal year (2017/2018).
15
XAFS measurement of simulated waste borosilicate glass samples (Joint research)
Nagai, Takayuki; Kobayashi, Hidekazu; Sasage, Kenichi; Ayame, Yasuo; Okamoto, Yoshihiro; Shiwaku, Hideaki; Yamanaka, Keisuke*; Ota, Toshiaki*
JAEA-Research 2017-005, 54 Pages, 2017/06
Addition of radioactive waste to a borosilicate frit affects the local structures of boron (B) and waste elements in a waste glass. Synchrotron XAFS measurement was applied to investigate the local structural changes by using simulated waste borosilicate glass samples. Following results were obtained by the B K-edge XAFS analysis. It was confirmed that B K-edge XAFS analysis enables us to discriminate sp$$^{2}$$ type boron (BO$$_{3}$$) from sp$$^{3}$$ type boron (BO$$_{4}$$). Addition of waste elements to a glass frit increases the percentage of BO$$_{3}$$ and decreases that of BO$$_{4}$$. By decreasing the SiO$$_{2}$$/Al$$_{2}$$O$$_{3}$$ ratio or increasing the (SiO$$_{2}$$+B$$_{2}$$O$$_{3}$$)/Al$$_{2}$$O$$_{3}$$ ratio in the glass composition, the BO$$_{3}$$ percentage increases and the BO$$_{4}$$ percentage decreases. Addition of P$$_{2}$$O$$_{5}$$ decreases the BO$$_{3}$$ percentage and increases the BO$$_{4}$$ percentage. Following results were obtained from XAFS measurement of the waste elements. Cerium (Ce) valence is more reduced with the increase of the B$$_{2}$$O$$_{3}$$ content. Addition of P$$_{2}$$O$$_{5}$$ has a tendency to reduce the Ce valence and to enhance deposition of Zr oxide. Deposition of ruthenium compounds separated from glass phase can not be improved by changing the B$$_{2}$$O$$_{3}$$ content. This study was performed as a part of the project, "Improvement of vitrification process of high-level radioactive liquid wastes" on the foundation business of the Agency for Natural Resources and Energy.
16
A Study of the evaluation of the excavation damaged zone in the Horonobe Underground Research Laboratory, 2; Investigation in the 250 m gallery (Joint research)
Aoyagi, Kazuhei; Kubota, Kenji*; Nakata, Eiji*; Suenaga, Hiroshi*; Nohara, Shintaro*
JAEA-Research 2017-004, 91 Pages, 2017/06
In this study, we performed seismic tomography, seismic refraction survey, resistivity tomography, and hydraulic tests to investigate the hydro-mechanical property of the excavation damaged zone (EDZ) in the 250 m gallery of the Horonobe Underground Research Laboratory. As a result of seismic tomography, seismic velocity is significantly decreased within 1 m from the gallery wall. The decrease of seismic velocity is related to the density of fracture induced around the gallery wall as a result of the gallery excavation. Thus the extent of the fractures induced by gallery excavation, i.e., EDZ fractures is clarified to be within 1.0 m from the gallery wall. The enhanced hydraulic conductivity was detected within 0.5 to 1.0 m from the gallery wall on the basis of the result of hydraulic tests. This is almost consistent with the extent of the region that seismic velocity is significantly decreased. Therefore, it is estimated that EDZ fractures induced around the gallery leads to the increase of hydraulic conductivity. In addition, the desaturation zone around the gallery is not induced as a result of resistivity tomography. From these results, the hydro-mechanical property of the EDZ is clarified in detail. Also, the in situ tests and evaluation method applied in this study are appropriate to investigate the EDZ in detail.
17
Research of the tasks on risk communication enforcement in Fiscal Year 2015; Contract research
Tanaka, Masaru*; Aoyama, Isao*; Ishizaka, Kaoru*; Ohata, Yuki*; Fukuike, Iori*; Kawase, Keiichi; Watanabe, Masanori; Tokizawa, Takayuki; Miyagawa, Hiroshi*; Ishimori, Yuu
JAEA-Research 2017-003, 65 Pages, 2017/06
JAEA Ningyo-toge Environmental Engineering Center and Fukushima Environmental Safety Center have same challenges in risk communication. As reference, similar domestic cases were investigated by our two Centers, and requirements for building long-term relationship were clarified. As follows; (1) Develop new relationship with various stakeholders in the region. (2) Make better use of existing resources (personnel, land and facilities, etc.). (3) Make a concerted effort to create new values with local stakeholders. (4) Make an opportunity which local stakeholders confirm safety and build confidence to the project. These efforts will enhance the opportunities for operators and residents to learn about environment management and environmental protection.
18
Groundwater pressure records by geochemical monitoring system in the Horonobe Underground Research Laboratory
Mezawa, Tetsuya; Mochizuki, Akihito; Miyakawa, Kazuya; Sasamoto, Hiroshi
JAEA-Data/Code 2017-010, 63 Pages, 2017/06
Japan Atomic Energy Agency (JAEA) has been conducting "geoscientific study" and "research and development on geological disposal" in the Horonobe Underground Research Laboratory (URL) for safe geological disposal of high-level radioactive waste. Geochemical parameters of groundwater pressure, pH, and oxidation-reduction potential in the deep groundwater has been continuously monitored by the monitoring system which was developed in the Horonobe URL Project. This report presents the data of groundwater pressure which have been obtained by the monitoring system installed at the 140 m and 350 m gallery. The data obtained until March 31, 2016 was summarized along with related information such as the specifications of boreholes and the excavation of the URL.
19
Geological and topographical data concerning normal faults (Kawaminami Fault) in the northern Miyazaki Plain, Southern Kyushu, Japan
Niwa, Masakazu; Kurosawa, Hideki*; Kosaka, Hideki*; Ikuta, Masafumi*; Takatori, Ryoichi*
JAEA-Data/Code 2017-009, 71 Pages, 2017/06
Changes of stress state due to the 2011 off the Pacific Coast of Tohoku Earthquake triggered normal displacements of faults that have not been regarded as active faults. In this study, geological survey for normal faults in coastal region was conducted in order to understand the mechanism of reactivation of inactive faults triggered by megathrust earthquakes. This report includes topographical and geological data obtained by field works in and around the Kawaminami Fault in northern margin of the Miyazaki Plain, with results of microscopic examination, analyses of X-ray diffraction and particle size distribution for clayey samples, analyses of tephra and plant opal, and radiocarbon dating.
20
History of the Mizunami Underground Research Laboratory Project
Sasao, Eiji
Genkan Senta Topikkusu, (122), p.4 - 12, 2017/06
JAEA is implementing the Mizunami Underground Research Laboratory Project, which is a geoscientific research program in crystalline rock environment in Mizunami City, Japan. This report summarise history, progress and present situation of the project.