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Title: SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement.

Abstract

This paper describes the knowledge advancements from the uncertainty analysis for the State-of- the-Art Reactor Consequence Analyses (SOARCA) unmitigated long-term station blackout accident scenario at the Peach Bottom Atomic Power Station. This work assessed key MELCOR and MELCOR Accident Consequence Code System, Version 2 (MACCS2) modeling uncertainties in an integrated fashion to quantify the relative importance of each uncertain input on potential accident progression, radiological releases, and off-site consequences. This quantitative uncertainty analysis provides measures of the effects on consequences, of each of the selected uncertain parameters both individually and in interaction with other parameters. The results measure the model response (e.g., variance in the output) to uncertainty in the selected input. Investigation into the important uncertain parameters in turn yields insights into important phenomena for accident progression and off-site consequences. This uncertainty analysis confirmed the known importance of some parameters, such as failure rate of the Safety Relief Valve in accident progression modeling and the dry deposition velocity in off-site consequence modeling. The analysis also revealed some new insights, such as dependent effect of cesium chemical form for different accident progressions. (auth)

Authors:
; ; ; ; ; ; ; ;  [1]
  1. US Nuclear Regulatory Commission, Washington, DC (United States)
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1140707
Report Number(s):
SAND2014-1344C
499305
DOE Contract Number:  
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the Probabilistic Safety Assessment and Management held June 22-27, 2014 in Honolulu, HI.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Gauntt, Randall O., Mattie, Patrick D., Bixler, Nathan E., Ross, Kyle, Cardoni, Jeffrey N, Kalinich, Donald A., Osborn, Douglas M., Sallaberry, Cedric Jean-Marie, and Ghosh, S. Tina. SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement.. United States: N. p., 2014. Web.
Gauntt, Randall O., Mattie, Patrick D., Bixler, Nathan E., Ross, Kyle, Cardoni, Jeffrey N, Kalinich, Donald A., Osborn, Douglas M., Sallaberry, Cedric Jean-Marie, & Ghosh, S. Tina. SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement.. United States.
Gauntt, Randall O., Mattie, Patrick D., Bixler, Nathan E., Ross, Kyle, Cardoni, Jeffrey N, Kalinich, Donald A., Osborn, Douglas M., Sallaberry, Cedric Jean-Marie, and Ghosh, S. Tina. 2014. "SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement.". United States. https://www.osti.gov/servlets/purl/1140707.
@article{osti_1140707,
title = {SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement.},
author = {Gauntt, Randall O. and Mattie, Patrick D. and Bixler, Nathan E. and Ross, Kyle and Cardoni, Jeffrey N and Kalinich, Donald A. and Osborn, Douglas M. and Sallaberry, Cedric Jean-Marie and Ghosh, S. Tina},
abstractNote = {This paper describes the knowledge advancements from the uncertainty analysis for the State-of- the-Art Reactor Consequence Analyses (SOARCA) unmitigated long-term station blackout accident scenario at the Peach Bottom Atomic Power Station. This work assessed key MELCOR and MELCOR Accident Consequence Code System, Version 2 (MACCS2) modeling uncertainties in an integrated fashion to quantify the relative importance of each uncertain input on potential accident progression, radiological releases, and off-site consequences. This quantitative uncertainty analysis provides measures of the effects on consequences, of each of the selected uncertain parameters both individually and in interaction with other parameters. The results measure the model response (e.g., variance in the output) to uncertainty in the selected input. Investigation into the important uncertain parameters in turn yields insights into important phenomena for accident progression and off-site consequences. This uncertainty analysis confirmed the known importance of some parameters, such as failure rate of the Safety Relief Valve in accident progression modeling and the dry deposition velocity in off-site consequence modeling. The analysis also revealed some new insights, such as dependent effect of cesium chemical form for different accident progressions. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/1140707}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Feb 01 00:00:00 EST 2014},
month = {Sat Feb 01 00:00:00 EST 2014}
}

Conference:
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