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AbstractAbstract
[en] One design of the passive residual heat removal (PRHR) system of nuclear reactor was presented. The PRHR system removes the residual heat of reactor to heat sink by natural circulation of three loops under accident condition. To verify the ability of the PRHR system, RETRAN02 code was used. Reference to the MUTSU parameters, numerical calculation simulating the residual heat removal under 100% rated condition was carried out for the system design. And several key factors affecting the capability of residual heat removal were analysed
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Record Type
Journal Article
Journal
Chinese Journal of Nuclear Science and Engineering; ISSN 0258-0918;
; v. 23(1); p. 32-38

Country of publication
AUXILIARY SYSTEMS, AUXILIARY WATER SYSTEMS, COMPUTER CODES, CONVECTION, COOLING SYSTEMS, ENERGY SYSTEMS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, HEAT TRANSFER, MASS TRANSFER, MATHEMATICAL SOLUTIONS, POWER REACTORS, PROPULSION REACTORS, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, REMOVAL, SAFETY, SHIP PROPULSION REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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