Abstract: Prototype Fast Breeder Reactor (PFBR) is a 500MWe pool type, sodium-cooled nuclear reactor, which is presently in an advanced stage of construction. Prototype Fast Breeder Reactor consists of Primary Sodium Circuit (PSC), Secondary Sodium Circuits (SSC), Safety Grade Heat Removal Circuits (SGDHRC) and Steam-Water Circuit (SWC). The primary sodium circuit removes the nuclear heat generated in the core and transfers it to the secondary sodium circuits through Intermediate Heat Exchangers (IHXs). The secondary sodium circuits, in turn, transfers the heat to steam/water circuit through Steam Generators (SGs). The decay heat is removed by sodium to sodium heat decay heat exchanger (DHX) and in turn sodium to air heat exchanger (AHX). The boundaries of sodium systems of Prototype Fast Breeder Reactor is designed so as to have an extremely low probability of leakage, rapidly propagating failure and rupture under the static & dynamic loads expected during various operating conditions. The degradation of material properties (e.g. effect of sodium, temperature and irradiation), transients, residual stresses, flaw size etc. are the important considerations, which were taken into account. Austenitic stainless steels of grade 316LN were used as major structural materials for IHX & DHX and modified 9Cr-1 Mo was used as the principal material of construction for the SG & AHX. Most of the Nuclear Steam Supply System (NSSS) components are thin walled and require manufacturing in separate nuclear clean halls to achieve high levels of quality. The welding standards and acceptance criteria of PFBR equipment are more stringent compared to ASME/other International standards. Various control measures and quality assurance are instituted during each and every stage of raw material procurement, welding, fabrication, non-destructive examinations, testing, handling, erection and post erection preservation to ensure high degree of reliability against failure for the design service life of 40 years. This paper highlights the challenges involved in welding and fabrication of various heat exchangers for 500MWe Prototype Fast Breeder Reactor.
Keywords: Quality Management, Welding, Non-destructive examination, Sodium systems.
Title: QUALITY MANAGEMENT DURING TUBE BUNDLE FABRICATION OF HEAT EXCHANGERS FOR 500 MWe PROTOTYPE FAST BREEDER REACTOR
Author: R.G.Rangasamy, Prabhat Kumar
International Journal of Management and Commerce Innovations
ISSN 2348-7585 (Online)
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