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 (TH) model and severe accident (SA) 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 a hypothetic unmitigated LT SBO at peach bottom #1 boiling water reactor (BWR) reactor nuclear power plants (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 TH calculations made by using maap code at the EC Joint Research Centre.
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April 2018
Research-Article
Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants
Monica Vela-Garcia
Monica Vela-Garcia
EC JRC—Joint Research Centre,
Directorate G—Safety & Security,
Nuclear Reactor Safety
& Emergency Preparedness,
Petten 1755 ZG, The Netherlands
e-mail: Monica.VELA-GARCIA@ec.europa.eu
Directorate G—Safety & Security,
Nuclear Reactor Safety
& Emergency Preparedness,
Petten 1755 ZG, The Netherlands
e-mail: Monica.VELA-GARCIA@ec.europa.eu
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Gueorgui I. Petkov
Monica Vela-Garcia
EC JRC—Joint Research Centre,
Directorate G—Safety & Security,
Nuclear Reactor Safety
& Emergency Preparedness,
Petten 1755 ZG, The Netherlands
e-mail: Monica.VELA-GARCIA@ec.europa.eu
Directorate G—Safety & Security,
Nuclear Reactor Safety
& Emergency Preparedness,
Petten 1755 ZG, The Netherlands
e-mail: Monica.VELA-GARCIA@ec.europa.eu
1Corresponding author.
Manuscript received September 30, 2016; final manuscript received January 6, 2018; published online March 5, 2018. Assoc. Editor: Asif Arastu.
ASME J of Nuclear Rad Sci. Apr 2018, 4(2): 020913 (4 pages)
Published Online: March 5, 2018
Article history
Received:
September 30, 2016
Revised:
January 6, 2018
Citation
Petkov, G. I., and Vela-Garcia, M. (March 5, 2018). "Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants." ASME. ASME J of Nuclear Rad Sci. April 2018; 4(2): 020913. https://doi.org/10.1115/1.4038928
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