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Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition

ナトリウム冷却高速炉における崩壊熱除去系システム運転時の炉内熱流動評価法開発のためのPLANDTL-2ナトリウム試験予備解析

小野 綾子; 田中 正暁; 三宅 康洋*; 浜瀬 枝里菜; 江連 俊樹

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

ポンプなどの動力に頼らない自然循環方式崩壊熱除去システムは、ナトリウム冷却高速炉の安全性向上に効果的であると認識されている。本論文では、浸漬型冷却器(DHX)やラッパー管のギャップも含めた炉心内の熱流動挙動を評価できる数値解析手法を確立するために、DHXと炉上部プレナムを模したPLANDTL-2におけるナトリウム試験の予備解析を行い、解析モデルの妥当性について述べた。

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 methodologies for the sodium-cooled fast reactor from the viewpoint of the safety enhancement. In this paper, the numerical simulation results of the preliminary analysis for the sodium experiment with the apparatus of PLANDTL-2, in which the core and the upper plenum with a dipped-type direct heat exchanger (DHX) were modeled, were discussed, in order to establish appropriate numerical models for the reactor core including the gap region among the subassemblies and the DHX.

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