Dynamic Analysis of Fast Reactor Scenario by Using DANESS Code

For a sustainable nuclear power generation, a spent fuel (SF) or transuranic (TRU) element reduction has become an important issue, which is also a main goal of the Generation-IV (Gen-IV) reactor system. As one of the Gen-IV reactor, the Korea advanced liquid metal reactor (KALIMER) has been studied. Recently, KALIMER with a low and high conversion ratio (CR) has been studied for a break-even core or burning TRU. A dynamic analysis method has been widely used for the fuel cycle analysis. In this study, the system dynamic DANESS (Dynamic Analysis of Nuclear Energy System Strategies) code was used for the fast reactor (FR) scenario analysis. It was developed for the fuel cycle study by Argonne National Laboratory (ANL). In this study, the KALIMER scenarios were analyzed with different conversion ratios (CR) for investigating the impact of the CR on SF or out-pile TRU inventory. Also, the long-term heat (LTH) load of the SF to the repository was analyzed