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research-article

Severe accident context evaluation for long-term station blackout in BWR NPPs

[+] Author and Article Information
Gueorgui Petkov

Independent Consultant, Volewijkshof 20, 1031 AH Amsterdam, the Netherlands
petkovgi@yahoo.com

Monica Vela-Garcia

EC JRC − Joint Research Centre, Directorate G − Safety & Security, Nuclear Reactor Safety & Emergency Preparedness, Petten 1755 ZG, the Netherlands
monica.vela-garcia@ec.europa.eu

1Corresponding author.

ASME doi:10.1115/1.4038928 History: Received September 30, 2016; Revised January 06, 2018

Abstract

The realistic study of dynamic accident context is an invaluable tool to address the uncertainties and their impact on safety assessment and management. The capacities of the Performance Evaluation of Teamwork (PET) procedure for dynamic context quantification and determination of alternatives, coordination and monitoring of human performance and decision-making are discussed in this paper. The procedure is based on a thorough description of symptoms during the accident scenario progressions with the use of thermo-hydraulic model and severe accident codes (MELCOR and MAAP). The opportunities of PET procedure for context quantification are exemplified for the long-term station blackout (LT SBO) accident scenario at Fukushima Daiichi #1 and an hypothetic unmitigated LT SBO at Peach Bottom #1 BWR Reactor NPPs. The context quantification of these LT SBO scenarios is based on the IAEA Fukushima Daiichi accident report, "State-of-the-Art Reactor Consequence Analysis" and thermo-hydraulic calculations made by using MAAP code at the EC Joint Research Centre.

Copyright (c) 2017 by ASME
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