Measurement and Analysis of an Angular Neutron Flux on a Beryllium Slab Irradiated with Deuterium-Tritium Neutrons
Author:
Affiliation:
1. Japan Atomic Energy Research Institute, Department of Nuclear Engineering, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE87-A23504
Reference27 articles.
1. A Fusion Design Study of Nonmobile Blankets with Low Lithium and Tritium Inventories
2. The Influence of Design Variations on Controlled Thermonuclear Reactor Blanket Neutronic Performance Using Variational Techniques
3. Helium-Cooled Blanket Designs
4. Increase of Tritium Breeding Ratio by Blankets Having Front Breeder Zone in Fusion Reactors
5. Helium-Cooled, Flibe Breeder, Beryllium Multiplier Blanket
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