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ナトリウム冷却高速炉の炉心崩壊熱除去に関する研究; 炉内直接冷却器による容器内冷却特性

Study on decay heat removal in sodium-cooled fast reactors; In-vessel cooling characteristics by direct heat exchanger

江連 俊樹 ; 小野島 貴光; 田中 正暁 ; 亀山 祐理*

Ezure, Toshiki; Onojima, Takamitsu; Tanaka, Masaaki; Kameyama, Yuri*

ナトリウム高速炉の安全性強化の一環として、浸漬型の直接熱交換器(DHX)による炉容器内部の自然循環のみで炉心領域を冷却する場合における炉心領域の冷却挙動把握を目的としてPLANDTL-2を実施した。試験の結果、DHXからの冷却材が炉心領域に潜り込む条件下における、炉心領域の温度分布を定量把握すると共に、チャンネル間に生じる浮力差による流量再配分により、炉心中段領域の温度分布が平坦化することを把握した。

As a part of safety enhancement of sodium-cooled fast reactors, experiments was carried out using PLANDTL-2 facility to grasp the core cooling behavior only relying on the natural circulation inside the vessel using dipped-type DHX. As the result, temperature distributions in the core were quantitatively grasped under a situation where cold coolant from DHX penetrated the core. Furthermore, it was observed that temperature distribution at the middle height of core became flat due to the flow redistribution among heating channels resulting from the buoyancy balance between channels.

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