Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 Reactor

Author: Kordyukov A. G.  

Publisher: Springer Publishing Company

ISSN: 1063-4258

Source: Atomic Energy, Vol.97, Iss.2, 2004-08, pp. : 564-570

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Abstract