Measurements of the Neutron Spectra from Materials Used in Fusion Reactors and Calculations Using the ENDF/B-III and -IV Neutron Libraries
Author:
Affiliation:
1. Lawrence Livermore Laboratory, Livermore, California 94550
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE76-A26854
Cited by 28 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 model of the 14MeV neutrons source term, for numerical solution of the transport equation to be used in BNCT simulation;Annals of Nuclear Energy;2012-04
2. Validation of Nuclear Calculations with the FENDL/E-1.1 and JENDL Fusion File Based on a Bulk-Shielding Experiment of a Large Type 316 Stainless Steel Assembly;Fusion Technology;1998-08
3. Measurement and Calculations of Angular Neutron Flux Spectra from Iron Slabs Bombarded with 14.8-MeV Neutrons;Nuclear Science and Engineering;1993-09
4. Analyses of 14 MeV Neutron Transport in Spherical Iron Assemblies with New Double-Differential56Fe Cross-Section Data;Fusion Technology;1992-05
5. Bulk Shielding Experiments on Large SS316 Assemblies;Fusion Technology;1992-05
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