Preliminary Results of Benchmark Tests on JENDL-2
スポンサーリンク
概要
著者
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TAKANO Hideki
Japan Atomic Energy Research Institute
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KIKUCHI Yasuyuki
Japan Atomic Energy Research Institute
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NARITA Tsutomu
Japan Atomic Energy Research Institute
関連論文
- Japanese Evaluated Nuclear Data Library Version 3 Revision-3 : JENDL-3.3
- Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinide
- ICONE11-36475 Research and Development on Accelerator-driven Transmutation System at JAERI
- ICONE11-36245 RECENT ACTIVITIES OF PB-BI TECHNOLOGY FOR ADS AT JAERI
- Japanese Evaluated Nuclear Data Library Version 3 Revision-2 : JENDL-3. 2
- Temperature Dependence of Parameters Used in Intermediate Treatment of Resonance Absorption
- Evaluation of neutron nuclear data for uranium-233.
- Evaluation of neutron nuclear data of chromium, iron and nickel for fusion neutronics application.
- Multi-level correction to breit-wigner single-level formula.
- 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.
- Effective multiplication factors and reaction rates calculated with fission spectra of U-235,U-238 and Pu-239.
- Preliminary Results of Benchmark Tests on JENDL-2
- Doppler effect of structural materials in fast reactors.
- Intermediate Neutron Resonance Absorption with Interference Scattering in Heterogeneous Systems
- Number of Resonances to be Adopted for Obtaining Practically Reliable Cross Section Curves
- Accuracy of Analytical Treatments for Resonance Absorption in Doppler Resonance Regions
- Effect of Resonance Scattering of Sodium on Resonance Absorption of U-238
- Effect of fission gas release on burnup characteristics and void reactivity in HCLWRs.
- Build-up and decay of actinide nuclides in fuel cycle of nuclear reactors.