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Comparison of certain methods of calculating neutron fluxes in a reactor fuel channel

✍ Scribed by Yu. P. Elagin; A. S. Il'yashenko; V. A. Lyul'ka; T. S. Poveshchenko; N. V. Sultanov

Publisher: Springer US
Year: 1980
Tongue: English
Weight: 309 KB
Volume: 48
Category: Article
ISSN: 1573-8205
DOI: 10.1007/bf01142143

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