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Experimental assessment of computer codes used for safety analysis of integral reactors
Author(s) -
A. A. Fal’kov,
V. S. Kuul',
O. B. Samoilov
Publication year - 1995
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/115099
Subject(s) - guard (computer science) , nuclear engineering , pressurizer , computer science , environmental science , engineering , mechanical engineering , coolant , programming language

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