The Thermal Neutron Spectrum in a Heterogeneous Reactor
Author:
Affiliation:
1. Japan Atomic Energy Research Institute, Tokai-Mura, Ibaragi-Ken, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE59-A25607
Reference2 articles.
1. The Thermal Spectrum of an Intermediate Assembly
2. BNL-325 “Neutron Cross Sections,” U.S. Govt. Printing Office, Washington, D.C.
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1. Numerical Solution to Space-Angle Energy-Dependent Neutron Integral Transport Equation;Journal of Nuclear Science and Technology;1971-03
2. Method for Calculating Average Thermal Neutron Parameters;Nuclear Science and Engineering;1967-04
3. Approximation for the Calculation of the Generalized First-Flight Collision Probability;Nuclear Science and Engineering;1966-10
4. The Generalized First-Flight Collision Probability in the Cylindricalized Lattice System;Nuclear Science and Engineering;1966-01
5. Spatial energy distribution of thermal neutrons in a heterogeneous reactor;Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology;1965-08
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