Analysis of MH-1A Loss of Coolant Accident
ARMY ENGINEER REACTORS GROUP FORT BELVOIR VA ENGINEERING DIV
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Analyses of a postulated loss of coolant accident LOCA for the MH- 1A Nuclear Power Plant are presented for large and intermediate size breaks in the primary system. Methods and assumptions consistent with AEC Interim Acceptance Criteria were used in evaluating the performance of the Emergency Core Cooling System ECCS. The computer codes RELAP-3 for reactor system blowdown and THETAl-B for fuel element heatup were used to perform these calculations at a core power of 49.5 MWt. The results of the core temperature transient for various break conditions are presented and the required cooling capability of a system meeting the AEC interim criteria is discussed.
- Nuclear Power Plants and Fission Reactor Engineering