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革新的水冷却炉(FLWR)高転換型炉心の熱水力設計

Thermal-hydraulic design of high conversion type core of FLWR

小林 登; 大貫 晃; 内川 貞夫; 大久保 努

Kobayashi, Noboru; Onuki, Akira; Uchikawa, Sadao; Okubo, Tsutomu

革新的水冷却炉(FLWR)の増殖型炉心と高転換型炉心とが燃料集合体以外の原子炉システムを変更することなく運転可能であることを示すため、自然循環冷却システムを採用した高転換型炉心の熱水力設計を行った。設計解析ではTRAC-BF1コードを使用し、従来の知見を反映した熱水力相関式を選択した。同一の原子炉圧力容器並びに燃料集合体入口オリフィスにより増殖型炉心と高転換型炉心とを成立させることを設計目標として、燃料集合体下部タイプレートでの圧力損失(形状損失)及び給水温度を調整することで、核設計上の要求事項(炉心平均ボイド率50%以下)並びに限界出力比の目標(CPR$$>$$1.3)を満足することを目指した。その結果、現行BWRと同等の下部タイプレート形状損失を採用し、給水温度を505Kとすることで成立する見通しを得た。

A thermal-hydraulic design of the high-conversion (HC) type core of the innovative water reactor for flexible fuel cycle (FLWR) was constructed under the natural circulation core cooling, in order to achieve that HC-FLWR core can be converted to a breeder type one. The criteria on the thermal-hydraulic design of HC-FLWR were that the average void fractions in the core was smaller than 50%, and that the critical power ratio was larger than 1.3. The criterion on void fractions was determined from the nuclear design of HC-FLWR. The length of the chimney and the settings of the inlet orifice are common in both types of cores. The coefficient of the lower tie-plate of the HC-FLWR core and the temperature of the feed water were parametrically changed. Consequently, the design criteria were satisfied by adopting the setting of the form loss coefficients of the lower tie-plate comparable to those of the current BWRs and by lowering the feed water temperature to 505 K.

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