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Decay heat experiment on thirty-two fusion reactor relevant materials irradiated by 14-MeV neutrons

Fujio Maekawa, Yujiro Ikeda1999年Fusion Engineering and DesignIF 1.7出版社

AbstractHighly accurate calculation of decay heat is important in safety designs of fusion reactors against loss of coolant/flow accidents. To provide experimental data of decay heat needed for validation of the design calculations, a systematic decay heat experiment was performed. Thirty-two fusion reactor relevant materials were irradiated by 14-MeV neutrons, and decay heat produced in the materials was measured by the Whole Energy Absorption Spectrometer in a cooling time period from 1 min to 400 days with typical experimental errors of 6–10%. Source neutron flux spectra at irradiation positions, which were needed for successive analyses, were determined. Lessons about sequential reactions, impurities, reactions induced by low energy neutrons and radiolysis which should be considered in activation analyses for fusion reactors were learned from the experimental analyses. The experimental data with the source neutron conditions are to be used for investigating the validity of decay heat calculation codes, activation cross section libraries and decay data libraries.

日本語訳

核融合炉の安全設計において、冷却材喪失事故に対する崩壊熱の高精度な計算は重要である。設計計算の検証に必要な崩壊熱の実験データを提供するため、系統的な崩壊熱実験を実施した。32種類の核融合炉関連材料に14-MeV中性子を照射し、材料中で生成される崩壊熱を全エネルギー吸収スペクトロメータにより、1分から400日までの冷却時間にわたって測定し、典型的な実験誤差は6〜10%であった。後続の解析に必要な照射位置における中性子源スペクトルを決定した。実験解析から、核融合炉の放射化解析において考慮すべき逐次反応、不純物、低エネルギー中性子による反応、および放射線分解に関する知見が得られた。実験データは中性子源条件とともに、崩壊熱計算コード、放射化断面積ライブラリ、および崩壊データライブラリの妥当性検証に使用される。

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