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Riemke, R.A.; Chow, H.; Kiser, D.M.; Ogden, D.M.
Idaho National Engineering Lab., Idaho Falls (USA)1984
Idaho National Engineering Lab., Idaho Falls (USA)1984
AbstractAbstract
[en] RELAP5/MOD2 is a pressurized water reactor (PWR) system transient analysis code which can be used for simulation of a wide variety of PWR system transients of interest in light water reactor (LWR) safety analysis. The code models have been designed to permit simulation of postulated accidents ranging from large break loss-of-coolant accidents to operational transients. Purpose of this paper is to present the status of RELAP5/MOD2 and to show calculation results for a SEBAN reflood test, a series of Semiscale natural circulation tests, and a H. B. Robinson Unit 2 main steamline break plant transient
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1984; 6 p; Joint meeting of the American Nuclear Society and the Atomic Industrial Forum; Washington, DC (USA); 11-16 Nov 1984; CONF-841105--43; Available from NTIS, PC A02/MF A01; 1 as DE85003264
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Conference
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