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 Issue dateSiteTitle
NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project31 October 2022NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project
ML21197A06720 July 2021Memo to Kevin Hsueh Re RES Iar FFRD CST
ML21179A34028 June 2021Fast Code Assessment for TRISO Fuels Summary Memo
ML21075A14822 March 2021High-Assay-Low-Enriched-Uranium Impact on Storage and Transportation Criticality
ML21076A41617 March 2021Metallic Fuel Assessment in Fast Summary Memo
ML19196A30630 April 2019NuScaleNon-Proprietary - Independent Melcor Confirmatory Analysis for NuScale Small Modular Reactor
ML19196A31830 September 2018NuScaleNon-Proprietary - Independent Assessment of In-Vessel Retention and Steam Explosion for the NuScale Small Modular Reactor, Res/Fscb 2018-02
NUREG-2206, - Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Reactors with Mark I and Mark II Containments.31 March 2018NUREG-2206 - Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Reactors with Mark I and Mark II Containments.
ML22154A1736 October 2017NSIR_UserNeed_Task2_(RES_HEsm)_06102017 - Guidance for Performing a Spent Fuel Assembly Adiabatic Heatup Calculation
ML11256A02330 September 2011Peach Bottom
Surry
NUREG-1953 Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models - Surry and Peach Bottom.
ML20198L0936 November 199705200003Revised, Assessment of Ex-Vessel Steam Explosions in AP600 Advanced Pressurized Water Reactor
ML20073E17225 July 199405200002Forwards Rept Entitled, Analysis of Ex-Vessel Steam Explosions for Combustion Engineering Sys 80+ Using Gtsf Computer Code. Provides Comments on Central,Outer & Multiple Instrument Tube Failures
ML19339K49628 February 199305200001Final Rept, Assessment of Ex-Vessel Fuel-Coolant- Interaction Energetics for GE Abwr.