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高温ガス炉のための動特性評価手法の開発(JAEA/INL共同研究)

Development of reactor dynamics method for HTGR under JAEA/INL collaborative research

本多 友貴; 佐藤 博之; 中川 繁昭; Bayless, P.*; Strydom, G.*; Baker, R. I.*; Gougar, H.*; 坂場 成昭

Honda, Yuki; Sato, Hiroyuki; Nakagawa, Shigeaki; Bayless, P.*; Strydom, G.*; Baker, R. I.*; Gougar, H.*; Sakaba, Nariaki

原子力機構と米国アイダホ国立研究所(INL)は、日本の高温工学試験研究炉(HTTR)、米国の炉外試験装置(HTTF)等の試験データ(公開資料)、コード及びモデルの相互活用により、高温ガス炉用シミュレーション手法の検証・高度化を目指した協力研究を開始した。本研究は、炉心入口と炉心出口の冷却材の温度差が大きく過渡時の温度挙動が複雑となる高温ガス炉のための動特性評価手法の構築及びHTTRの炉心流量喪失試験(LOFC試験)データを用いた検証を目指す。本報では、使用するコード及びモデルの概要、並びにHTTRのLOFC試験のシミュレーション結果を示す。

The collaborative research between JAEA and Idaho National Laboratory (INL) has been initiated for development and validation of high temperature gas-cooled reactor simulation methods and models. The disclosure data from experiments of High Temperature engineering Test Reactor (HTTR) and High Temperature Test Facility (HTTF), simulation codes and models were exchanged. As one of the collaborative research, it has been focused on construction of reactor dynamics method for High Temperature Gas-cooled Reactor (HTGR) in which transient response of core temperature is complicated with large temperature difference between reactor inlet and reactor outlet. In addition, it has been planned to validate these codes and models with experiment data of Loss of forced cooling (LOFC) test using HTTR. This presentation introduces the outline of the codes and model, and shows the results of LOFC test simulation.

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