Sensitivity of sodium void worth in fast reactors to cross sections.

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概要

• 論文の詳細を見る
• 一般社団法人 日本原子力学会の論文

著者

• HASEGAWA Akira

  Japan Atomic Energy Research Institute

• KIKUCHI Yasuyuki

  Japan Atomic Energy Research Institute

• TAKEDA Toshikazu

  Faculty of Engineering, Department of Nuclear Engineering, Osaka University

• AOYAMA Takafumi

  Faculty of Engineering, Department of Nuclear Engineering, Osaka University

関連論文

• Japanese Evaluated Nuclear Data Library Version 3 Revision-3 : JENDL-3.3
• Japanese Evaluated Nuclear Data Library Version 3 Revision-2 : JENDL-3. 2
• Evaluation of neutron nuclear data for uranium-233.
• Evaluation of neutron nuclear data of chromium, iron and nickel for fusion neutronics application.
• Second version of Japanese Evaluated Nuclear Data Library (JENDL-2)
• Sensitivity of sodium void worth in fast reactors to cross sections.
• Evaluation of neutron cross section of 27 fission product nuclides important for fast reactor.
• Preliminary Results of Benchmark Tests on JENDL-2
• Drift and diffusion coefficients for asymmetric cells of fast critical assembly.
• Build-up and decay of actinide nuclides in fuel cycle of nuclear reactors.

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