Browse wiki

Iodine +, Cesium +, Iron +, Nickel +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Molybdenum +, Zirconium +, Lead +, Chromium +  and Cerium +

Regulatory Guide 1.174 +, ML16096A374 +, ML12332A057 +, ML110980205 +, NUREG/CR-7155, State-of-the-Art Reactor Consequence Analyses Project. Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station +, ML15224A001 +, NUREG/CR-7245, State-of-the-Art Reactor Consequence Analyses (Soarca) Project Sequoyah Integrated Deterministic and Uncertainty Analyses +, ML17062A466 +, ML110970450 +, ML18122A012 +, ML20100J883 +, ML20304A339 +, ML092870775 +, ML21321A161 +, ML19064B355 +, ML031140094 +, ML041380224 +, ML11228A232 +, ML110110152 +, ML101130544 +, ML16068A170 +, NUREG/CR-7110 Volume 2, Rev 1 State-of-the-Art Reactor Consequence Analyses Project Volume 2: Surry Integrated Analysis +  and NUREG/CR-7110 Volume 1, Rev 1 State-of-the-Art Reactor Consequence Analyses Project: Peach Bottom Integrated Analysis +

Bixler N +, Gauntt R +, Ghosh S +, Mattie P +, Osborn D +, Ross K +, Hossein Esmaili +, Salman Haq +, Dennis M +, Katie Wagner +, Office of Nuclear Regulatory Research +, Brooks D +, Hathaway A +, Sandia +, Faucett C +  and Haskin T +

NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +  and NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +

Cs-137 +  and I-131 +

Westinghouse +, General Electric +  and Target Rock +

NUREG/CR-7037 +, NUREG/CP-0152 +, NUREG/BR-0359 +, NUREG/CR-7155, State-of-the-Art Reactor Consequence Analyses Project. Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station +, NUREG/CR-6119 +, NUREG/CR-7245, State-of-the-Art Reactor Consequence Analyses (Soarca) Project +, NUREG-1788 +, NUREG-1922 +, NUREG/CR-6995 +, NUREG-1771 +, NUREG-2195 +, NUREG/CR-5528 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, NUREG/CR-6791 +, NUREG/CR-2239, Forwards Slides/Handout Used at 821110 Presentation of NUREG/CR-2239 Re Sandia Siting or Consequences Study. Transcript of Meeting in PDR Did Not Include Slides +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project +, NUREG-7245 +, NUREG/CR-7262, State-of-the-Art Reactor Consequence Analyses Project Uncertainty Analysis of the Unmitigated Short-Term Station Blackout of the Surry Power Station +, NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +, NUREG-1935, Notice of Public Meeting to Discuss the State-of-the-Art Reactor Consequence Analyses (Soarca) Research Project +  and NUREG/CR-7110, Official Exhibit - ENT000457-00-BD01 - NUREG/CR-7110, Vol. 2, State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 2) +

1x10-6 +, 1x10-7 +, 1x10-5 +, 2x10-6 +, 4x10-5 +, 3x10-7 +, 5x10-6 +, 2x10-5 +, 3x10-5 +, 1x10-12 +, 1x10-10 +, 3x10-6 +, 8x10-6 +  and 9x10-7 +

Ohio +, Tennessee +, Pennsylvania +, Georgia +, Washington +, Virginia +, South Carolina +, New York +, Michigan +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Shield Building +, Main Steam Line +, Safety Relief Valve +  and Main Steam +

Probabilistic Risk Assessment +, FLEX +, Fukushima Dai-Ichi +, Earthquake +, Fuel cladding +, Fatality +  and Manual Operator Action +