Dynamic modeling of steam water system of prototype fast breeder reactor using RELAP code

• Dynamic modeling of steam water system of an LMBFR using RELAP5 code.
• Analysis of events managed by power setback procedure in the plant.
• Selection of parameters and their thresholds for the power setback procedure.

The safety of a fast breeder reactor based nuclear power plant with an intermediate coolant loop between the primary and tertiary circuit, depends on the correct functioning of actions initiated by the balance-of-plant (tertiary) systems. Comfortable time will be available for such actions to ensure reactor safety. Perturbations in the Balance-of-Plant (BoP) influence the transient sequence of safety-relevant parameters of the plant in a benign manner. However, for complete and realistic prediction of transient behavior of the whole plant, dynamic models for BoP systems are required to be developed. This paper describes modeling of BoP system of PFBR using RELAP5/MOD 3.4 code. Some of the important transients in the BoP system, which are managed by reactor power setback procedure have been analysed using this code to verify the effectiveness of the procedure adopted.