A Formalism for Calculation of Neutron Induced Gamma-Ray Production Cross Sections and Spectra
Author:
Affiliation:
1. Lawrence Radiation Laboratory, University of California, Livermore, California 94550
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE68-A19730
Cited by 10 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. A Semiempirical Method to Calculate Continuum Gamma-Ray Spectra and Multiplicities from Neutron-Induced Reactions;Nuclear Science and Engineering;1996-10
2. Double-Differential Gamma-Ray Production Cross Sections of Al, Fe and Si for Neutrons Between 8.5 and 14.2 MeV;Nuclear Data for Science and Technology;1992
3. Photon Production Cross Section for181Ta;Nuclear Science and Engineering;1988-04
4. Structural, heavy coolant, and material cross-section data;Progress in Nuclear Energy;1984-01
5. Calculation of Gamma-Ray Production Cross Sections at Neutron Energies of 1–20 MeV;Journal of Nuclear Science and Technology;1983-04
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