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Jin, Young Ho; Jang, S. C.; Son, Y. S.
Korea Atomic Research Inst., Daeduk (Korea, Republic of)2003
Korea Atomic Research Inst., Daeduk (Korea, Republic of)2003
AbstractAbstract
[en] Various accidents are simulated to demonstrate the capability of MARS code for low power/shutdown accident. These are stuck open of PSV in POS2, loss of shutdown cooling accident in POS3, loss of shutdown cooling accident and loss of coolant accident in POS4, and loss of shutdown cooling accident with gravity feed from RWST in POS5. For these accidents, major thermal hydraulic variables, such as the RCS pressure, water level in the reactor vessel, the pressure and the water level in the steam generator, heat transferred through steam generators, total release of water outside of RCS, boiling time in the reactor core, the uncovery time in the core, and core damage time, are compared. The results of MARS code is very close to the results of RELAP5 code for these accidents. This means that the capability of MARS code is equivalent to the RELAP5 code in simulating accidents in shutdown condition
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Mar 2003; 91 p; 72 figs, 6 tabs
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