Analysis of Post Irradiation Experiments in PWR Using New Nuclear Data Libraries.

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概要

• 論文の詳細を見る

• For the precise calculation of the burnup of minor actinide isotopes, a code system-SWAT has been developed. This system analyzes burnup problems with neutron spectrum that depends on the type of a reactor and the irradiation history, using latest evaluated nuclear data files JENDL-3 or ENDF/B-VI. The post irradiation test in TRINO and the recent experiment in typical PWRs in Japan were analyzed with SWAT. These analyses show that the results of U and Pu for high burnup fuels almost agree with experimental results but those for middle burnup fuels do not agree with them. The results for Am and Cm isotopes still have large discrepancy. The average C/E of <SUP>243</SUP>Am is 0.79, and that of <SUP>244</SUP>Cm is 0.70 for high burnup (33, 000 MWd/tU) samples. <BR>For middle burnup (25, 000 MWd/tU) samples, the C/E for <SUP>244</SUP>Cm is over 2.0. The discrepancy is partially explained by considering the power peaking history of first cycle and second cycle.

• 一般社団法人 日本原子力学会の論文

著者

• Hirakawa Naohiro

  Department Of Nuclear Engineering Tohoku University

• Iwasaki Tomohiko

  Department Of Cardiology Heart Institute Of Japan Tokyo Women's Medical College

• Suyama Kenya

  Department Of Fuel Cycle Safety Research Tokai Research Establishment Japan Atomic Energy Research I

• HIRAKAWA Naohiro

  Department of Nuclear Engineering, Faculty of Engineering, Tohoku University

• IWASAKI Tomohiko

  Department of Nuclear Engineering, Faculty of Engineering, Tohoku University

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