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論文

Double diffusive dissolution model of UO$$_{2}$$ pellet in molten Zr cladding

伊藤 あゆみ*; 山下 晋; 田崎 雄大; 垣内 一雄; 小林 能直*

Journal of Nuclear Science and Technology, 60(4), p.450 - 459, 2023/04

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

The rapid dissolution of UO$$_{2}$$ in molten Zr that could occur during fuel-cladding liquefaction at high temperatures and its kinetics were reformulated considering the convective mass transfer and the chemical effect at the UO$$_{2}$$/Zr interface. The mass transfer coefficient of U was obtained as a correlation including the aspect ratio term by CFD analysis. To explain the gap between the rapid dissolution rate observed in the experiments and the density-driven convective mass transfer, we introduced an idea in which the eutectic melting at the UO$$_{2}$$/Zr interface promotes the grain detachment owing to infiltration of the U-Zr-O liquid into the UO$$_{2}$$ grain boundaries. The developed model was validated with UO$$_{2}$$-Zr crucible experiments at 2273 and 2373 K. The calculated mass percentage ratios of U/Zr agreed with the measurements and the transition times from rapid saturation to precipitation were consistent with the metallographic observations.

口頭

Improving chemical thermodynamics knowledge of severe accidents within the OECD-TCOFF2 Project

Journeau, C.*; Bechta, S.*; Komlev, A.*; 倉田 正輝; 多木 寛; 松本 俊慶; Mohamad, A. B.; Barrachin, M.*; Quaini, A.*; Bottomley, D.*; et al.

no journal, , 

The OECD project TCOFF-2 (Thermodynamic Chemistry of Fission Products - Part 2) is an extension of the original project that was part of the near-term projects intended to support the Fukushima Dai-ichi decommissioning efforts. This second part continues to be mainly financed by Japanese Ministry (MEXT) with JAEA-CLADS support. TCOFF2 started in August 2022 and includes certain new material requirements compared to the first TCOFF project. These are increased emphasis on accident tolerant fuels (ATFs), certain actinides and fission products related to volatility/leachability but also certain combinations of the ceramic oxide systems important for MCCI behaviour. Following a PIRT review of phenomena in TCOFF 1, there was in TCOFF2 a Task 1 to prioritise current needs, particularly for relevance to severe accident phenomena and alternative materials (ATFs). This included a re-evaluation and ranking of the thermodynamic systems to make a Systems Identification and Ranking Table (SIRT) for the improvement of the thermodynamic database foreseen in TCOFF2. The further systems for evaluation were then proposed by the partners according to their particular requirements; this resulted in over 150 thermodynamic systems. In the mid-year meeting (June 2023) discussions were made to rationalise these into the most important 20 systems. The rationale for the reduction of systems to this limit will be explained in the talk, both those systems that were omitted as well as those finally included. These systems will then be used as a priority list of work for the experimental call to members that will be launched by the TCOFF-2 project towards the end of the year 2023 with the intention to initiate the first projects soon afterwards.

口頭

燃料デブリ周辺物質の分析結果に基づく模擬デブリの合成による実機デブリ形成メカニズムの解明,6; 金属デブリによる下部プレナム損傷挙動の評価

永江 勇二; 佐藤 拓未; 伊藤 あゆみ*; 植田 滋*

no journal, , 

東京工業大学、東北大学及び原子力機構で実施した小規模試験結果を総括し、過酷事故時における金属デブリによる下部プレナム損傷挙動を評価した結果を報告する。(1)溶融ジルコニウム濃度が炉心下部構造物との反応性に寄与していること、(2)溶融金属プール形成時における酸化物デブリとの反応においてもジルコニウムが反応に寄与し、ウラン-ジルコニウムの酸化物層とステンレス鋼-ジルコニウムの低酸素濃度金属層に分離することを確認した。各種反応によりジルコニウム濃度は低下する傾向にあるが、低酸素濃度の金属デブリがペデスタル部で溶融プールを形成する可能性が考えられる。金属デブリが高ジルコニウム濃度の場合、構造材と共晶反応を起こし、比較的低温で構造物の溶融が進行する可能性がある一方、ジルコニウム濃度が低い場合、構造材との反応は限定的であり、温度上昇による熱破損やクリープ破損などが支配的になると考えられる。

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