ナトリウム冷却高速炉の崩壊熱除去システム運用時の原子炉容器内熱流動解析評価手法整備; 崩壊熱除去試験を対象とした妥当性確認解析

Development of numerical estimation method for thermal hydraulics in reactor vessel of sodium-cooled fast reactor under decay heat removal operation; Validation practice with decay heat removal test

田中 正暁  ; 三宅 康洋*; 浜瀬 枝里菜 ; 江連 俊樹 

Tanaka, Masaaki; Miyake, Yasuhiro*; Hamase, Erina; Ezure, Toshiki

ナトリウム冷却高速炉の安全性強化の観点から極めて有効な方策である自然循環崩壊熱除去時において、事故時を含むあらゆる条件下で原子炉容器内の熱流動場を予測できる解析評価手法の構築が重要となっている。そこで、ナトリウム試験装置(PLANDTL-2)で実施した崩壊熱除去試験を対象に妥当性確認解析を実施した結果を報告する。

For safety enhancement of sodium-cooled fast reactor, decay heat removal system (DHRS) by using the natural circulation without depending on the pump as the mechanical equipment is recognized as one of the most effective methods. The numerical estimation method which can predict thermal hydraulic phenomena in the reactor vessel during DHRS operation is necessarily required. In this study, the numerical analysis of a sodium test for decay heat removal conducted at the scaled sodium experimental facility named PLANDTL-2 was implemented to validate the RV-CFD model.