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Report No.
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Application analysis of SSC-L(1); Analysis of MONJU primary loop natural circulation

Yoshikawa, Shinji* ; Iguchi, Tatsuro*

SSC-L(Super System Code - Loop version) is a thermo-hydraulic transients analysis code in LMFBRs, developed at Brookhaven National Laboratory in USA. This code is capable of both analyses of normal operation and accident. It allows free allocation of the components in heat transport systems, and arbitrary representation of the heat transport systems. Since the introduction of this code in June 1980, a large effort has been devoted to facilitate and validate the use of the SSC code for MONJU plant transient analysis. This report describes analysis of reactor shutdown transient in MONJU plant from full-power operation to natural circulation with simultaneous all pumps trip. In this transient a pressure loss characteristics of the primary loop and a frictional characteristics of the primary pump dominate coolant thermohydraulic behavior. In order to investigate the sensitivity of the loop and pump characteristics for the transient, following two cases were analized. (1)Characteristics of the loop pressure loss and the pump frictional torque based on the physical theory and experimental data. (2)Under the natural circulation, pressure losses of core, check valves, and stopped pumps have great effect on flow rate. Results are summarized as follows: (1)Flow coastdown transient up to natural circulation is characterized by the pump speed. In the range of flow rate under 50% of the rated value, the pump frictional torque plays a important role in the determining the flow rate. (2)Under the natural circulation, pressure losses of core, Check valves, and stopped pumps have great effect on flow rate. (3)The maximum coolant temperature at the top of the core during the transient is determined by the degree of mismatch of thermal power and flow rate. In this analysis, the maximum coolant temperature, is higher than both in full power operation and in natural circulation.

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