Validation of RELAP/SCDAPSIM/MOD3.4 for research reactor applications

The RELAP/SCDAPSIM/MOD3.4 code, designed to predict the behavior of reactor systems during normal and accident conditions, is being developed as part of the international SCDAP Development and Training Program (SDTP). RELAP/SCDAPSIM/MOD3.4 uses publicly available RELAP/MOD3.3 and SCDAP/RELAP5/MOD3.2 models, developed by the US Nuclear Regulatory Commission, in combination with (a) new models for fission product transport and deposition, fuel assembly behavior, and in-vessel melt retention, (b) advanced programming and numerical techniques, and (c) integrated graphics displays. The RELAP5 and SCDAP models have been validated for a wide range of accident conditions using a variety of experiments and plant data. However, the validation of the models for research reactor applications has been much more limited. As a result, a group within SDTP, including the Nuclear Research Institute, Rez (Czech Republic), National Nuclear Energy Agency of Indonesia, China Institute of Atomic Energy, and Bangladesh Atomic Energy Research Establishment, has started work to validate the code for a variety of research reactor designs including TRIGA and other unique research reactors. This paper describes the reactor designs currently being considered in the study, the development and qualification of input models for the facilities, and the transients being analyzed as part of this effort. (authors)