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Validation of evaluation method of feedback reactivity for plant dynamics analysis code during unprotected loss of heat sink event in sodium-cooled fast reactors

プラント動特性解析コードのフィードバック反応度評価手法のナトリウム冷却高速炉ULOHS事象への適用性確認

吉村 一夫; 堂田 哲広 ; 田中 正暁 ; 山野 秀将  ; 井川 健一*

Yoshimura, Kazuo; Doda, Norihiro; Tanaka, Masaaki; Yamano, Hidemasa; Igawa, Kenichi*

プラント動特性解析コードSuper-COPDに組み込まれたフィードバック反応度評価手法の妥当性確認のため、米国高速実験炉EBR-IIで行われた、炉停止失敗と2次主循環ポンプ停止を重畳させたULOHS模擬試験(BOP-302R, BOP-301試験)のベンチマーク解析を実施した。炉心入口温度及び原子炉出力の実測データと解析結果の比較から、Super-COPDのフィードバック反応度評価手法のULOHS事象への適用性を確認した。

The numerical results of the benchmark analyses for the unprotected loss of heat sink (ULOHS) tests in the pool-type experimental SFR in the United States, EBR-II (BOP-302R and BOP-301) are discussed in order to validate the evaluation method of the reactivity feedback equipped in the in-house plant dynamics analysis code named Super-COPD. By comparing the numerical results and the experimental data, the profiles of the increase of the core inlet temperature and the decrease of the reactor power calculated by Super-COPD were comparable with those of the experimental data and the applicability of the evaluation method for the reactivity feedback was indicated during the ULOHS event.

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