Nuclear Data Sheets

Nuclear Data Sheets

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文章名称 引用次数
ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data 149
TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology 50
Reference Cross Sections for Charged-particle Monitor Reactions 31
Evaluation of the Neutron Data Standards 21
CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen 12
Nuclear Data Sheets for A=170 11
Evaluation of Neutron Reactions on Iron Isotopes for CIELO and ENDF/B-VIII.0 11
Nuclear Data Sheets for A=164 9
The Prompt Fission Neutron Spectrum of U-235(n, f) below 2.5 MeV for Incident Neutrons from 0.7 to 20 MeV 8
IAEA CIELO Evaluation of Neutron-induced Reactions on U-235 and U-238 Targets 6
Nuclear Data Sheets for A=39* 5
Nuclear Data Sheets for A=155 4
Nuclear Data Sheets for A=59 4
Evaluations of Energy Spectra of Neutrons Emitted Promptly in Neutron-induced Fission of U-235 and Pu-239 4
Nuclear Data Sheets for A=188 4
Recommended Nuclear Data for the Production of Selected Therapeutic Radionuclides 4
Improved Cumulative Fission Yield Measurements with Fission Spectrum Neutrons on U-235 3
Nuclear Data Sheets for A=171 3
Nuclear Data Sheets for A=136 3
Nuclear Data Sheets for A=177 3
Nuclear Data Sheets for A=140 3
Nuclear Data Sheets for A=38 2
Nuclear Data Sheets for A=50 2
Nuclear Data Sheets for A=254 2
Nuclear Data Sheets for A=217 2
The Scale Method as an Approach for Prompt Fission Neutron Spectra Analysis and Evaluation 1
Nuclear Data Sheets for A=298 1
Nuclear Data Sheets for A=73 1
Nuclear Data Sheets for A=82 1
Pu-239(n,gamma) from 10 eV to 1.3 MeV 1
Evaluation of Neutron-induced Cross Sections and their Related Covariances with Physical Constraints 1
Nuclear Data Sheets for A=218 1
Nuclear Data Sheets for A=105 0
Nuclear Data Sheets for A=292 0