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Core thermal-hydraulic analysis during dipped-type direct heat exchanger operation in natural circulation conditions

浸漬型DHXを用いた自然循環崩壊熱除去時の炉心内熱流動解析

浜瀬 枝里菜 ; 堂田 哲広 ; 小野 綾子 ; 田中 正暁 ; 三宅 康洋*; 今井 康友*

Hamase, Erina; Doda, Norihiro; Ono, Ayako; Tanaka, Masaaki; Miyake, Yasuhiro*; Imai, Yasutomo*

ナトリウム冷却高速炉の安全性強化のため、自然循環崩壊熱除去システムにおいて浸漬型直接炉内冷却器(D-DHX)の採用が検討されている。D-DHXを稼働した場合、炉心と炉上部プレナム間の相互作用が生じるため、炉容器全体を一括して取り扱う炉容器内多次元熱流動解析評価手法(RV-CFDモデル)の構築が必要となる。本研究では、計算負荷低減のため、集合体のモデル化に着目し、既存のサブチャンネル解析手法を参考にした解析手法をRV-CFDモデルの炉心部に採用した。本モデルの適用性を確認するため、ナトリウム試験装置PLANDTL-1を対象に試験解析を実施した。その結果、D-DHXからの低温ナトリウムが炉心部に潜り込む際の炉容器内流況をとらえるとともに、集合体内温度分布の傾向を再現でき、本モデルの適用性を確認した。

To enhance the safety of sodium-cooled fast reactors, a dipped-type direct heat exchanger (D-DHX) has been investigated in a natural circulation decay heat removal system. During the D-DHX operation, the core-plenum interactions occurs, therefore, a thermal-hydraulic analysis model in the reactor vessel for computational fluid dynamics code (RV-CFD model) is necessarily required. In this study, the application of the subchannel analysis method for subassemblies to the RV-CFD model was attempted to reduce the calculation costs. Analysis results were compared to the experimental data obtained in the sodium experimental apparatus PLANDTL-1. As the result, the behavior of cold sodium into the simulated core was well grasped and the calculated sodium temperature in the core had good agreement with the experimental result. The applicability of the RV-CFD model was confirmed.

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