Abstract
Abstract In 500 MWe Prototype Fast Breeder Reactor (PFBR), the Primary Sodium Pump (PSP) contained in the primary circuit circulates sodium through the core. The PSP is supported on the roof slab. The space between the roof slab and sodium free surface is filled with argon. PSP will be lowered slowly, using a flask, into the main vessel (MV) after the completion of preheating and sodium filling of the main vessel. Pump inside the flask will be at ambient condition before lower ng into the sodium pool. While lowering PSP into MV sodium, one of the critical welds near the shell-flange junction at the discharge nozzle will experience thermal stress due to the hot shock offered by the sodium. The governing failure mode to ensure the structural integrity of the PSP is the creep damage developed in the weld near the junction of flange due to the discontinuity stresses that would be locked up the weld while lowering. This paper addresses the thermo-mechanical analysis carried out towards establishing the preheating temperature and speed of lowering the pump in the sodium pool. The PSP may be take in out for inspection/maintenance and lowered it back into the sodium pool around 5-10 times during the plant life. Based on this investigation, the PSP preheat temperature and lowering rate has been recommended.
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