In-Pool By-Pass Pipe is a structure which connects the 2 In-Pool Pipes instead of In-Pile Test Section(IPS). It is designed to accommodate the 17.5 MPa and 80 ℃ under the consideration of the FTL pre-operation conditions but the need for high temperature, over 200 ℃, during FTL pre-operation make the additional assessment to be performed. For this study 2 models are used. One is an In-Pool By-Pass Pipe model which affected by HANARO water's elevation, another is an In-Pool By-Pass Pipe Nozzle which has 2 boundary conditions; water and air. After the heat transfer analysis linear stress analysis was performed to achieve Tresca stress. In the region of high stress model's detailed behavior is observed by ASME SectionⅢ NB code. Consequentially it concluded that the model of In-Pool By-Pass Pipe Structure is in reasonable agreement with those code.

The small break loss-of-coolant accidents for the HANARO fuel test loop have been predicted by MARS code. Conservative method was used for the prediction of the loss-of-coolant accidents. The maximum peak cladding temperature was calculated as 1286K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. The maximum peak cladding temperature occurred for the cold leg break in the HANARO pool. The hydrogen generation and oxidation of the fuel cladding were also negligible. Consequently, it is ensured that the emergency cooling water system for the HANARO fuel test loop is appropriate for the small break loss-of-coolant accidents.

The nuclear fuel cladding temperatures of the HANARO fuel test loop have been calculated by MARS code for the large break loss-of-coolant accidents. Conservative method was used for the analysis of the loss-of-coolant accidents. Consequently, the maximum peak cladding temperature was predicted as 1235K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. This means that the cooling capability of the emergency cooling water system for the HANARO fuel test loop is sufficient for the large break loss-of-coolant accidents.

The conservative method on the analysis of loss-of-coolant accidents for the HANARO fuel test loop was established based on the guide of evaluation method for the emergency core cooling systems of pressurized light water reactors. The evaluation models, the Moody model for discharge rate calculation and the Baker-Just model for water-metal reaction calculation, were used. In order to calculate conservative peak cladding temperatures for accidents the multipliers to the correlations of heat transfer coefficients in the MARS were also introduced. Consequently it is found that the maximum peak cladding temperature predicted by using the conservative method is sufficiently greater than that calculated by using the best-estimated models.