Abstract
A Shutdown Heat Removal Test (SHRT) conducted using the EBR-II reactor at Argonne National Laboratory (ANL) in the U.S.A. was proposed by International Atomic Energy Agency (IAEA) in June 2012 as a benchmark problem. The SHRT-17 test is loss-of-flow (LOF) test, and the SHRT-45R is an unprotected loss-of-flow (ULOF) test. We use the plant system code NETFLOW++ and the neutronics code ERANOS to analyze the two tests. The SHRT-17 test is calculated using only the NETFLOW++ code because it is a purely thermal hydraulic problem. To calculate the SHRT-45R test, we should have delayed neutron data and reactivity coefficients calculated by the ERANOS code. These parameters are used in the NETFLOW++ code to conduct a neutronics - thermal hydraulic coupled calculation. In the present work, major parameters of the plant are predicted with good accuracy. But we overestimated the peak temperature of coolant because of the slightly weak reactivity feedback coefficient for sodium density change in the fuel region. When the reactivity feedback coefficient is adjusted, good agreement of the peak coolant temperature is obtained.
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