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Preliminary accident analysis for a conceptual design of a 10 MW multi-purpose research reactor

10MW級多目的研究炉の概念設計のための予備的な事故解析

Park, C.; 谷本 政隆; 今泉 友見; 宮内 優; 伊藤 正泰; 神永 雅紀

Park, C.; Tanimoto, Masataka; Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Kaminaga, Masanori

本報告書は概念設計の段階にある10MW級の多目的研究炉(MRR)の設計実現性及び安全裕度の評価を行うため、流量喪失事故(LOFA)及び反応度事故(RIAs)時における燃料温度等の解析をRELAP5/MOD3コードを用いて実施した。この解析の結果、MRRの概念設計は安全裕度を持って実現可能であることが示された。また、同一事象に対し、研究炉の解析で広く用いられているPARET/ANLコードとEUREKA-2/RRコードを用いた適用性に関する比較評価を行い、これら3つの計算コードはある特定の条件下では若干異なる傾向を示したものの、解析全般に関しては、ほぼ同等の結果を得られることが示された。

Preliminary accident analysis has been carried out for a LOFA (Loss of Flow Accident) and RIAs (Reactivity Insertion Accidents) of the conceptual 10 MW MRR (multi-purpose research reactor) under design study by using the RELAP5/MOD3 code in order to provide the preliminary evaluation of safety margin as well as the intuitions to the design of the MRR. Input and modeling for the RELAP5/MOD3 simulations have also been described. The analysis results indicate that the concept of the MRR is feasible with practical safety margins. The same events have been also analyzed by using the PARET/ANL and the EUREKA-2/RR codes to compare the codes suitability, which have been widely used for the analysis of research reactors. Same geometric and modeling data used for the RELAP5/MOD3 have been used as long as they correspond to each code's input requirements. The three codes show the same or similar overall trends for the events analyzed, but show a small difference in a specific condition.

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