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SPECIAL SECTION PAPERS

Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants

[+] Author and Article Information
Gueorgui I. Petkov

Independent Consultant,
Volewijkshof 20,
Amsterdam 1031 AH, The Netherlands
e-mail: 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
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 4(2), 020913 (Mar 05, 2018) (4 pages) Paper No: NERS-16-1134; doi: 10.1115/1.4038928 History: Received September 30, 2016; Revised January 06, 2018

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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References

Petkov, G. , 2018, “ Enhancing Time-Dependent Criteria for Design-Basis and Design Extension Conditions Based on Human Performance Context Evaluation in ATWS Events,” ASME J. Nucl. Eng. Radiat. Sci. (accepted).
Vela-Garcia, M. , and Simola, K. , 2016, “ Evaluation of JRC Source Term Methodology Using MAAP5 as a Fast-Running Crisis Tool for a BWR4 Mark I Reactor,” Ann. Nucl. Energy, 96, pp. 446–454. [CrossRef]
NEA, 2016, “ Benchmarking of Fast-Running Software Tools Used to Model Releases During Nuclear Accidents,” Nuclear Energy Agency, Paris, France, Report No. NEA/CSNI/R(2015)19. https://www.oecd-nea.org/nsd/docs/2015/csni-r2015-19.pdf
Kostov, E. , and Petkov, G. , 2014, “ Dynamic Context Quantification for Design Basis Accidents List Extension and Timely Severe Accident Management,” Probability Safety Assessment and Management (PSAM12), Honolulu, HI, June 22–27, Paper No. 490. https://www.researchgate.net/publication/290549871_Dynamic_context_quantification_for_design_basis_accidents_list_extension_and_timely_severe_accident_management
IAEA, 2015, “ The Fukushima Daiichi Accident, Technical Volume 1: Description and Context of the Accident,” Annex I of Technical Volume 1 (Unit 1 Sequence of Events), International Atomic Energy Agency, Vienna, Austria, accessed Feb. 9, 2018, http://www-pub.iaea.org/MTCD/Publications/PDF/AdditionalVolumes/P1710/Pub1710-TV1-Web.pdf
NRC, 2013, “ State-of-the-Art Reactor Consequence Analyses—Volume 1: Peach Bottom Integrated Analysis,” Nuclear Regulatory Commission, Albuquerque, NM, Report No. NUREG/CR-7110. https://www.nrc.gov/docs/ML1202/ML120260675.pdf
Petkov, G. , and Kostov, E. , 2013, “ Risk Resonance Context in Nuclear Facilities,” PSAM 2013 Topical Conference, Tokyo, Japan, Apr. 14–18, Paper No. PSAM2013-1029.
Petkov, G. I. , and Vela-Garcia, M. , 2016, “ Severe Accident Context Evaluation for BWR NPPs Based on Long-Term Station Blackout,” ASME Paper No. ICONE24-60923.
Petkov, G. , Kostov, E. , Filipov, K. , Stefanova, A. , Atanasova, B. , Andreeva, M. , and Groudev, P. , 2015, “ Dynamic Context Evaluation of Human Actions in Severe Accident Analysis and Management,” The Annual European Safety and Reliability Conference (ESREL), Zürich, Switzerland, Sept. 7–10, No. M18_764. https://ec.europa.eu/jrc/en/publication/dynamic-context-evaluation-human-actions-severe-accident-analysis-and-management
Sehgal, B. R. , 2015, “ Lecture 5: Environmental and Socio-Economic Impact of a Severe Accident,” Short Course on Severe Accident Methodology, AlbaNova University Center, Stockholm, Sweden.

Figures

Grahic Jump Location
Fig. 1

Primary pressure evolutions in the base case

Grahic Jump Location
Fig. 2

Comparison between “simplified” and “bunch” accident contexts of the Fukushima Daiichi NPP#1

Grahic Jump Location
Fig. 3

melcor and maap LT SBO base case CPs

Grahic Jump Location
Fig. 4

maap LT SBO case 1, 2, and 3 CPs

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