Japanese Evaluated Nuclear Data Library Version 3 Revision-2 : JENDL-3. 2
スポンサーリンク
概要
- 論文の詳細を見る
- 1995-12-25
著者
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SHIBATA Keiichi
Japan Atomic Energy Research Institute
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KAWANO Toshihiko
Kyushu University
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NAKAGAWA Tsuneo
Japan Atomic Energy Research Institute
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FUKAHORI Tokio
Japan Atomic Energy Research Institute
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OHSAWA Takaaki
Kinki University
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NAKAJIMA Yutaka
Research Organization for Information Science and Technology
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ZUKERAN Atsushi
Hitachi Ltd.
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ASAMI Tetsuo
Data Engineering, Inc.
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Chiba Satoshi
Japan Atomic Energy Agency
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Chiba S
Japan Atomic Energy Research Institute
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Watanabe T
National Institute For Fusion Science
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OHSAWA Takaaki
School of Science and Engineering, Kinki University
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MATSUNOBU Hiroyuki
Japanese Nuclear Data Committee
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Asami Tetsuo
Data Engineering Inc.
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Ohsawa Takaaki
School Of Science And Engineering Kinki University
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Sato Kazumichi
Department Of Energy Conversion Engineering Kyushu University
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Fukahori T
Japan Atomic Energy Agency
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Fukahori Tokio
Japan Atomic Energy Agency
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Chiba S
Japan Atomic Energy Res. Inst.
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Kanda Yukinori
Kyushu University
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KOSAKO Kazuaki
Sumitomo Atomic Industries
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WATANABE Takashi
Kawasaki Heavy Industries, Ltd.
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NAKAJIMA Yutaka
Japan Atomic Energy Research Institute
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KIKUCHI Yasuyuki
Japan Atomic Energy Research Institute
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MATSUNOBU Hiroyuki
Sumitomo Atomic Energy Industries, Ltd.
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KAWAI Masayoshi
Toshiba Corporation
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IGARASI Sin-iti
Nuclear Energy Data Center
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KOSAKO Kazuaki
Nuclear Energy Data Center
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Zukeran Atsushi
Nippon Advanced Information Service Co. Ltd.
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Zukeran Atsushi
Energy Research Laboratory Hitachi Ltd.
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Shibata Keiichi
Japan Atomic Energy Agency
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Igarasi Sin-iti
Data Engineering Ltd.
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Nakagawa Tsuneo
Japan Atomic Energy Agency
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Sato K
Department Of Energy Conversion Engineering Kyushu University
関連論文
- Achievement of 10 keV Central Electron Temperatures by ECH in LHD
- Evaluation of Neutron Nuclear Data on Arsenic-75 for JENDL-4
- Calculation of Neutron Cross Sections on ^Zr for JENDL-4
- Calculation of Neutron Nuclear Data on Selenium Isotopes for JENDL-4
- Coupled-Channels Analysis of Nucleon Interaction Data of ^ Si up to 200 MeV Based on the Soft Rotator Model
- Japanese Evaluated Nuclear Data Library Version 3 Revision-3 : JENDL-3.3
- Coupled-Channels Optical Potential for Interaction of Nucleons with ^C up to 150MeV in the Soft-Rotator Model
- The ^C(p, p'3α)Breakup Reaction Induced by 14, 18 and 26 MeV Protons
- Measurement of Gamma-Ray Production Double-Differential Cross Sections for the Spallation Reaction Induced by 0. 8, 1. 5 and 3. 0 GeV Protons
- Measurement of Neutron-Production Double-Differential Cross Sections for Nuclear Spallation Reaction Induced by 0. 8, 1. 5 and 3. 0 GeV Protons
- JENDL-4.0: a new library for nuclear science and engineering
- Prevention of Reversed Flow in Gas Divertor with High Vacuum Chamber
- 表面磁場による完全β=1プラズマ保持配位への自発転移
- シート・プラズマ中のヘリウムイオン温度
- LHDダイバータ模擬実験のための高熱流シートプラズマ開発研究
- Evaluation of Neutron Nuclear Data on Bromine and Krypton Isotopes for JENDL-4.0
- JENDL Actinoid File 2008
- JENDL-4.0: A New Library for Nuclear Science and Engineering
- Extensive Study of the Soft-Rotator Model Hamiltonian Parameters for Medium and Heavy Even-Even Nuclei
- Determination of Lambda-Mode Eigenvalue Separation of a Thermal Accelerator-Driven System from Pulsed Neutron Experiment
- Phenomenological Nuclear Level Densities using the KTUY05 Nuclear Mass Formula for Applications Off-Stability
- Evaluation of Neutron Cross Sections of Carbon-12 for Energies up to 80 MeV
- Lifetime of Heavy Composite Systems Formed by Fusion between Heavy Nuclei
- Nuclear Level Structure, B(E2) Gamma-transitions and Nucleon Interaction Cata for ^Fe by a Unified Soft-rotator Model and Coupled-Channels Famework
- Simultaneous Evaluation of Fission Cross Sections of Uranium and Platonium Isotopes for JENDL-3.3
- Nucleon Optical Potential of Uranium-238 up to 150MeV
- Plasma Plugging in Gas Divertor
- Interchange Stability Criteria for Anisotropic Central-Cell Plasmas in the Tandem Mirror GAMMA 10
- シートプラズマを用いたイオンサイクロトロン加熱実験
- Analysis of Nucleon Scattering Data of ^Cr with a Coupling Scheme Built with the Soft-rotator Model
- Measurement of Gamma - Ray Production Double - Differential Cross Sections for 1.5 GeV π^+ Meson Incidence on Iron
- Experimental Neutron-Production Double-Differential Cross Section for the Nuclear Reaction by 1.5-GeV π^+ Mesons Incident on Iron
- Spallation Neutron Measurement by the Time-of-Flight Method with a Short Flight Path
- JENDL Fusion File 99
- Re-evaluation of Nuclear Data of Fission Product Nuclides for JENDL-3.2
- Evaluation of Neutron Nuclear Data for Mercury
- Japanese Evaluated Nuclear Data Library Version 3 Revision-2 : JENDL-3. 2
- Analysis of Neutron Spectra from Thick Targets Bombarded with 710-MeV Alpha Particles by Quantum Molecular Dynamics plus Statistical Decay Model
- Covariance Analyses of Self-Shielding Factor and Its Temperature Gradient for Uranium-238 Neutron Capture Reaction
- Measurement of Electric-Dipole Moment by Polarization Laser Spectroscopy
- Measurement of Dipole-Moment in Atomic Transitions under Strong External Magnetic Field
- Time-of-Flight Measurement of Photoneutrons from O^, Ca^, and P^
- Evaluation of Nertron-and Proton-induced Nuclear Data on ^Al up to 2GeV
- Validation of JENDL High-Energy File through Analyses of Spallation Experiments at Incident Proton Energies from 0.5 to 2.83 GeV
- Fusion Reactions in Supernovae and the Early Universe
- An Extended Rod Drop Method Applicable to Subcritical Reactor System Driven by Neutron Source
- JENDL-4.0 : A New Library for Nuclear Science and Engineering
- Oral Cytology in Patients with Necrotizing Sialometaplasia
- Calculation of Neutron Nuclear Data on Rubidium and Strontium Isotopes for JENDL-4
- Calculation of Neutron Nuclear Data on Molybdenum Isotopes for JENDL-4
- Calculation of Neutron Cross Sections on ^Y for JENDL-4
- Calculation of Neutron Cross Sections on ^Nb for JENDL-4
- Improved Infrared DIC-Video Microscopy and Its Application to Unstained Living Preparations
- Uranium-235 Neutron Capture Cross Section at keV Energies
- Improvement of Gamma-ray Production Data for JENDL-3.2
- Evaluation of Photonuclear Reaction Data on Tantalum-181 up to 140 MeV
- Three-Dimensional Benchmark Tests of ENDF/B-VI for Thermal Reactor Core
- Evaluation of Neutron Nuclear Data on Bromine and Krypton Isotopes for JENDL-4.0
- Uncertainty Analyses in the Resolved Resonance Region of ^U, ^U, ^Pu with the Reich-Moore R-Matrix Theory for JENDL-3.2
- Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment
- Validity of DWBA Calculations for Neutron Inelastic Scattering from Molybdenum Isotopes
- Estimation of Covariance Matrices for Nuclear Data of ^Np, ^Am and ^Am
- Feynman-α Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14MeV Neutron Source
- Analysis of n + 6Li Reactions Using the Continuum-Discretized Coupled-Channels Method
- Evaluation of Neutron Cross Sections of Hydrogen from 20 MeV to 1 GeV
- Analysis of n + ^6Li Reactions Using the Continuum-Discretized Coupled-Channels Method
- Surrogate Method (微視的核反応理論による物理)
- Monte Carlo simulation of prompt neutron emission during acceleration in fission
- Analysis of Nucleon Scattering Data of ^Cr with a Coupling Scheme Built with the Soft-rotator Model
- Coupled-channels Optical Model Analyses of Nucleon-induced Reactions for Medium and Heavy Nuclei in the Energy Region from 1keV to 200 MeV
- 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.
- Differential .ALPHA.-Protection Cross Sections of Iron and Nickel for 4.3 to 14.1 MeV Nertrons.
- Neutron resonance parameters of silver-107 and silver-109.
- Evaluation of neutron cross section of 27 fission product nuclides important for fast reactor.
- Preliminary Results of Benchmark Tests on JENDL-2
- Monte carlo evaluation of VHTR cell calculational model with emphasis on resonance integral.
- Build-up and decay of actinide nuclides in fuel cycle of nuclear reactors.