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Radiation protection calculations for an Am-Be neutron source
Annals of the ICRPWhen calculating dose rates around an Am–Be source, one typically focuses on the neutron emission. In high activity Am–Be sources, there is a need to consider two additional contributors to the dose: low-energy photon emission from the 241 Am decay (59.5 keV and an additional 4.4-MeV photon ...
Y, Fried +5 more
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An Assembly-Level Neutronic Calculation Method Based on LightGBM Algorithm
Annals of Nuclear Energy, 2021Jiejin Cai, Xuezhong Li, Sitao Peng
exaly
1987
The kerma heat production density, tritium production density, and dose in a lithiumfluoride pile with a deuterium-tritium neutron source were calculated with a data processing code, UFO, from the pulse height distribution of a miniature NE213 neutron spectrometer, and compared with the values calculated with a Monte Carlo code, MORSE-CV.
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The kerma heat production density, tritium production density, and dose in a lithiumfluoride pile with a deuterium-tritium neutron source were calculated with a data processing code, UFO, from the pulse height distribution of a miniature NE213 neutron spectrometer, and compared with the values calculated with a Monte Carlo code, MORSE-CV.
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On the Calculation of Neutron Lifetimes
Nuclear Science and Engineering, 1970openaire +1 more source
3D Neutronic/Thermal-Hydraulic Nuclear Reactor Core Calculation (NRCC) Code Development for PWRs
Progress in Nuclear Energy, 2020Mahdi Zangian
exaly
Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analysis
Journal of Nuclear Engineering, 2021William Wieselquist
exaly