Korea's Benchmark Results against Experimental Data from IEA-R1

Various thermal hydraulic codes have been used for the safety analyses of research reactors. One of them is RELAP5/MOD3, which is an internationally well known best estimate code. Although the code was originally developed for the thermal hydraulic transient analyses of nuclear power plants operating at high pressure and temperature, it has been widely used for safety analyses of research reactors operating at low pressure and temperature. The RELAP5/MOD3 code has been widely compared with other codes and experiments for application to research reactors, improvements against some models in the code have been suggested. Although great effort on the validation of the RELAP5/MOD3 code to research reactors has been carried out, code validation and improvements are still required. Benchmark calculations against the experimental data have been carried out.