Title :
Safety study and human factor assessment of end-shield draining event for 220MWe Indian PHWRs
Author :
Gautam, A.P. ; Krishnakumar, P. ; Hajela, S. ; Vijaya, A.K. ; Guptan, R.K. ; Malhotra, P.K. ; Dhame, S.P. ; Ghadge, S.G.
Author_Institution :
Nucl. Power Corp. India Ltd., Mumbai, India
Abstract :
In Indian PHWRs (Pressurized Heavy Water Reactors), one of the major functions of the end-shield cooling system is to maintain temperature across the end-shield components uniform and thereby minimizing thermal stresses. Safety analysis considers draining of water from end-shield cooling system as one of the postulated event. In the PSA (Probabilistic Safety Analysis) Level-l study, failure to manually shut-down the reactor following this event was found to be one of the major contributors to Severe Core Damage. The deterministic and probabilistic studies as detailed in the paper, realistically evaluate contribution of the postulated event of end-shield draining in core damage and make a major input to Risk Informed Decision Making.
Keywords :
decision making; fission reactor cooling; fission reactor core control; fission reactor safety; heavy water reactors; probability; risk analysis; PHWR; core damage analysis; end-shield cooling system; end-shield draining event analysis; human factor assessment; pressurized heavy water reactor; probabilistic safety analysis; risk informed decision making system; safety assessment; thermal stress analysis; Fabrication; Frequency modulation; Manuals; Niobium; Temperature distribution; CDF; PHWR; PSA; draining; end-shield;
Conference_Titel :
Reliability, Safety and Hazard (ICRESH), 2010 2nd International Conference on
Conference_Location :
Mumbai
Print_ISBN :
978-1-4244-8344-0
DOI :
10.1109/ICRESH.2010.5779615