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Neutron-physical and heat-engineering aspects of uranium-graphite reactors loaded with enriched-uranium fuel elements

✍ Scribed by Yu. A. Artel’nyi; P. M. Gavrilov; A. A. Tsyganov


Publisher
Springer US
Year
2006
Tongue
English
Weight
156 KB
Volume
101
Category
Article
ISSN
1573-8205

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