Evaluation of the offsite dose contribution to the global risk in a Steam Generator Tube Rupture scenario

M.J. Rebollo, C. Queral, G. Jimenez, J. Gomez-Magan, Meléndez, E. and M. Sanchez-Perea

Reliability Engineering and System Safety, 2016, vol. 147, issue C, 32-48

Abstract: The current main figure of merit for risk based decision making process based on Probabilistic Safety Assessment level 1 is usually related with the fuel failure (i.e., Peak Cladding Temperature (PCT)>1477.15K). In this approach, the core damage is the first and necessary step in a potential radiological release, being the containment failure the second one. Nevertheless, SGTR sequences in PWR plants are able to release large quantities of radioactive products without previous core damage or containment failure. For that reason, it seems necessary to analyze which sequences exceed the allowed offsite dose criteria prior to the core damage criterion.

Keywords: Integrated safety assessment (ISA); Steam generator tube rupture (SGTR); Dynamic event tree (DET). (search for similar items in EconPapers)
Date: 2016
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Citations: View citations in EconPapers (6)

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Persistent link: https://EconPapers.repec.org/RePEc:eee:reensy:v:147:y:2016:i:c:p:32-48

DOI: 10.1016/j.ress.2015.10.016

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