Literature review on experiments and models associated with degradation and oxidation of boron carbide control material during severe accidents
Zheng, X.; 石川 淳; 伊藤 裕人; 玉置 等史; 丸山 結
Zheng, X.; Ishikawa, Jun; Ito, Hiroto; Tamaki, Hitoshi; Maruyama, Yu
Boron carbide (B$$_{4}$$C) is one kind of neutron absorbing control rod/blade materials used in light water reactors (LWRs). In Fukushima Daiichi Nuclear Power Station (NPS), all units used B$$_{4}$$C as absorber material. The degradation of control rod/blade will affect the early phase of in-vessel core melt progression. Furthermore, the release of carbon compound gases including carbon dioxide (CO$$_{2}$$) as well as boron compounds due to the oxidation of B$$_{4}$$C with steam is possible to affect source terms of radioactive materials. Past experiments related to B$$_{4}$$C degradation and oxidation and numerical modeling in severe accidents codes are investigated in the current report with a main view to apply the acquired knowledge into the modification of THALES-2 developed at JAEA as an integral severe accident analysis code. The eutectic interactions of B$$_{4}$$C with other materials such as stainless steel and Zircaloy will lower the melting point of control rod/blade. The Nagase's correlations for eutectic interaction are selected as one of candidates to be applied into THALES-2. The oxidation reaction of B$$_{4}$$C with steam will release considerable amount of thermal energy, and form CO$$_{2}$$, boric acids and boron oxide, which could make an impact onto source terms by changing the pH value of a water pool where those dissolve. The IRSN correlation is chosen to be used in the modeling of oxidation reaction in THLAES-2.
使用言語 : English
報告書番号 : JAEA-Review 2014-016
ページ数 : 32 Pages
発行年月 : 2014/06
特許データ :
論文URL :
キーワード : 福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 :
登録番号 : RV20140016
抄録集掲載番号 : 42000696
Accesses  (From Jun. 2, 2014)
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