Unified Diffusion Coefficient for Analysis of Sodium-Void Worth in Fast Critical Assembly with Control-Rod Channels
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1981.9733231
Reference19 articles.
1. Anisotropic Neutron Diffusion in Lattices of the Zero-Power Plutonium Reactor Experiments
2. Improved Treatment of the Neutron Streaming Through Control Rod Followers in a Sodium-Cooled Fast Reactor
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1. Verification of Homogenization in Fast Critical Assembly Analyses;Journal of Nuclear Science and Technology;2006-11
2. A Simple Calculation of Control Assembly Effectiveness in a Liquid-Metal Fast Breeder Reactor by a Transport-Diffusion Equivalence Method;Nuclear Science and Engineering;1989-11
3. Prediction Uncertainty Evaluation Methods of Core Performance Parameters in Large Liquid-Metal Fast Breeder Reactors;Nuclear Science and Engineering;1989-10
4. Determination of Cell Averaged Diffusion Constants Based on Transport/Diffusion Perturbation Theory;Journal of Nuclear Science and Technology;1987-12
5. Worths and Interactions of Simulated Fast Breeder Reactor Control Rods in ZEBRA and SNEAK Assemblies;Nuclear Science and Engineering;1984-07
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