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Nuclear Technology Volume 207, 2021 - Issue 3: Selected papers from the 16th International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2019)
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Technical Papers

State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios

S. Tina Ghosha U.S. Nuclear Regulatory Commission, Washingon, District of Columbia20555Correspondence[email protected]
,
Hossein Esmailia U.S. Nuclear Regulatory Commission, Washingon, District of Columbia20555
,
Alfred Hathawaya U.S. Nuclear Regulatory Commission, Washingon, District of Columbia20555
,
Nathan Bixlerb Sandia National Laboratories, Albuquerque, New Mexico87185
,
Dusty Brooksb Sandia National Laboratories, Albuquerque, New Mexico87185
,
Matthew Dennisb Sandia National Laboratories, Albuquerque, New Mexico87185
,
Douglas Osbornb Sandia National Laboratories, Albuquerque, New Mexico87185
,
Kyle Rossb Sandia National Laboratories, Albuquerque, New Mexico87185
&
Kenneth Wagnerb Sandia National Laboratories, Albuquerque, New Mexico87185
 show all
Pages 441-451 | Received 16 Nov 2020, Accepted 11 Jan 2021, Published online: 22 Mar 2021

References

  • “State-of-the-Art Reactor Consequence Analyses (SOARCA) Report,” NUREG-1935, U.S. Nuclear Regulatory Commission (2012).
  • “State-of-the-Art Reactor Consequence Analyses (SOARCA) Project: Volume 1: Peach Bottom Integrated Analysis,” NUREG/CR-7110, Vol. 1, U.S. Nuclear Regulatory Commission (2013).
  • “State-of-the-Art Reactor Consequence Analyses (SOARCA) Project: Volume 2: Surry Integrated Analysis,” NUREG/CR-7110, Vol. 2, U.S. Nuclear Regulatory Commission (2013).
  • “State-of-the-Art Reactor Consequence Analyses (SOARCA) Project: Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station,” NUREG/CR-7155, U.S. Nuclear Regulatory Commission (2016).
  • “State-of-the-Art Reactor Consequence Analyses (SOARCA) Project: Sequoyah Integrated Deterministic and Uncertainty Analyses,” NUREG/CR-7245, U.S. Nuclear Regulatory Commission (2019).
  • “State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analysis of the Unmitigated Short-Term Station Blackout of the Surry Power Station,” draft report, ML15224A001, U.S. Nuclear Regulatory Commission (2015).
  • Regulatory Guide 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Rev. 3, U.S. Nuclear Regulatory Commission (2018).
  • “Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decisionmaking,” NUREG-1855, Rev. 1, U.S. Nuclear Regulatory Commission (2017).
  • S. T. GHOSH et al., “State-of-the-Art Reactor Consequence Analyses Project Uncertainty Analyses: Insights on Methodologies,” Proc. 2019 Int. Topl. Mtg. Probabilistic Safety Assessment (PSA 2019), Charlston, South Carolina, Apr. 28–May 3, 2019, American Nuclear Society (2019).
  • “Modeling Potential Reactor Accident Consequences,” NUREG/BR-0359, Rev. 3, U.S. Nuclear Regulatory Commission (2020).
  • “Benefits and Uses of the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project,” RIL20-03, ML20100J883, U.S. Nuclear Regulatory Commission (2020).

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