JENDL-4.0: a new library for nuclear science and engineering
スポンサーリンク
概要
著者
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IWAMOTO Osamu
Japan Atomic Energy Research Instiute
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SHIBATA Keiichi
Japan Atomic Energy Research Institute
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NAKAGAWA Tsuneo
Japan Atomic Energy Research Institute
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KATAKURA Jun-ichi
Japan Atomic Energy Research Institute
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Chiba Satoshi
Japan Atomic Energy Agency
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FURUTAKA Kazuyoshi
Japan Atomic Energy Research Institute
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IWAMOTO Nobuyuki
Japan Atomic Energy Agency
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ICHIHARA Akira
Japan Atomic Energy Agency
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KUNIEDA Satoshi
Japan Atomic Energy Agency
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OTUKA Naohiko
International Atomic Energy Agency
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OHSAWA Takaaki
School of Science and Engineering, Kinki University
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MURATA Toru
Japanese Nuclear Data Committee
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MATSUNOBU Hiroyuki
Japanese Nuclear Data Committee
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ZUKERAN Atsushi
Japanese Nuclear Data Committee
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KAMADA So
National Institute of Radiological Sciences
関連論文
- 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
- Coulomb Excitation of^Gd
- 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
- Design of a Compact 4π Ge Spectrometer for the Measurement of Neutron Capture Cross Sections of Minor Actinides
- Prompt Gamma Rays Emitted in Thermal-neutron Capture Reaction by ^Tc and Its Reaction Cross Section
- 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
- Evaluation of Nertron-and Proton-induced Nuclear Data on ^Al up to 2GeV
- 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
- Estimation of Beta- and Gamma-Ray Spectra for JENDL FP Decay Data File
- Possible Origin of the Gamma-ray Discrepancy in the Summation Calculations of Fission Product Decay Heat
- Fine Structure of Giant Resonance in the ^Si(γ, abs) Reaction
- Thermal-Neutron Capture Cross Sections and Resonance Integrals of the ^Se(n,γ)^Se Reactions
- Measurement of the Thermal Neutron Capture Cross Section and the Resonance Integral of the^Ag(n, γ)^Ag Reaction
- 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
- Calculation of Neutron Nuclear Data on Silicon Isotopes for JENDL-4
- Measurement of the Thermal Neutron Capture Cross Section and the Resonance Integral of the ^Sr(n, ν)^Sr Reaction
- Uranium-235 Neutron Capture Cross Section at keV Energies
- Improvement of Gamma-ray Production Data for JENDL-3.2
- Measurement of Effective Neutron Capture Cross Section of ^Ho using Two Step Irradiation Technique
- 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
- New Evaluation of Neutron Nuclear Data for Zinc Isotopes
- 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
- 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 of chromium, iron and nickel for fusion neutronics application.
- Differential .ALPHA.-Protection Cross Sections of Iron and Nickel for 4.3 to 14.1 MeV Nertrons.
- Evaluation of neutron cross section of 27 fission product nuclides important for fast reactor.