Thermal-Reactor Lattice Analysis Using ENDF/B-IV Data with Monte Carlo Resonance Reaction Rates
Author:
Affiliation:
1. Brookhaven National Laboratory, National Neutron Cross Section Center Upton, New York 11973
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE76-A26836
Cited by 7 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. Analysis of Thermal Reactor Benchmarks with Design Codes Based on ENDF/B-V Data;Nuclear Technology;1985-11
2. Meeting cross-section requirements for nuclear-energy design;Annals of Nuclear Energy;1982-01
3. The Effects on Reactivity Coefficients of Spectral Shifts Induced by Doppler Broadening;Nuclear Science and Engineering;1981-11
4. Combined estimate of neutron-flux functional by means of correlated selection;Soviet Atomic Energy;1981-09
5. Evaluation of the lattice physics code ‘MURLI’ for light water systems;Annals of Nuclear Energy;1981-01
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