Second version of Japanese Evaluated Nuclear Data Library (JENDL-2)

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概要

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• Compilation of the second version of Japanese Evaluated Nuclear Data Library (JENDL-2) has been completed. The aim of JENDL-2 is the applications to fast, thermal and fusion reactors, and shielding problems. The evaluated data for 181 nuclides were stored in the ENDF/B-IV format. Various benchmark tests have been performed, and applicability of JENDL-2 was confirmed for the fast and thermal reactor calculations and for the shielding problems. In this review, evaluation work for JENDL-2 is briefly described, and the results of the benchmark tests are summarized.

• 一般社団法人 日本原子力学会の論文

著者

• Asami Tetsuo

  Japan Atomic Energy Research Institute

• Kanda Yukinori

  Department Of Energy Conversion Engineering Kyushu University

• KIKUCHI Yasuyuki

  Japan Atomic Energy Research Institute

• MATSUNOBU Hiroyuki

  Sumitomo Atomic Energy Industries, Ltd.

• Nakagawa Tsuneo

  Japan Atomic Energy Agency

• KANDA Yukinori

  Department of Energy Conversion Engineering, Kyusyu University

• KAWAI Masayoshi

  Nippon Atomic Industry Group Co., Ltd.

関連論文

• Japanese Evaluated Nuclear Data Library Version 3 Revision-3 : JENDL-3.3
• JENDL Actinoid File 2008
• Two-Dimensional Analysis of Energy Conversion Efficiency for a Traveling Wave Direct Energy Convertor
• Plasma Energy Recovery from a D-3^He Inertial Confinement Fusion Reactor
• Simultaneous Evaluation of Fission Cross Sections of Uranium and Platonium Isotopes for JENDL-3.3
• Re-evaluation of Nuclear Data of Fission Product Nuclides for JENDL-3.2
• Japanese Evaluated Nuclear Data Library Version 3 Revision-2 : JENDL-3. 2
• JENDL-4.0 : A New Library for Nuclear Science and Engineering
• The Parameters of the 0.099-eV Neutron Resonance in Sm-149
• Uranium-235 Neutron Capture Cross Section at keV Energies
• Measurement of Helium Production Cross Sections of Stainless Steels for 14 MeV Neutrons
• Measurement of Proton-Induced Helium Production Cross Sections for Aluminum and Nickel below 16 MeV
• Estimation of Covariance Matrices for Nuclear Data of ^Np, ^Am and ^Am
• Absolute calibration by helium-ion-implanted samples for helium accumulation method applied to neutron dosimetry.
• Measurement of helium production cross section of aluminium for 14.8MeV neutrons.
• 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)
• Resonance parameters of tantalum-181 in neutron energy range from 100 to 4,300eV.
• Method for decision of nuclear reaction model parameters.
• 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
• Activation Cross Sections for (n, p) and (n, α) Reactions on Nd, Sm, Yb and Lu at 14.6 MeV
• Build-up and decay of actinide nuclides in fuel cycle of nuclear reactors.
• Shield Optimization Study for Choke Coil of Tandem Mirror Fusion Reactor "GAMMA R"
• Significance of covariance matrices in nuclear data evaluation.

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