The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Technical Letter Reports – 2021

Document Number Title Publish Date
RES-DE-REB-2021-1 The State of Technology of Application of Digital Twins 06/15/2021
RES-DE-REB-2021-2 Assessment of Non-Gross Breaches in Spent Fuel Cladding during Drying Operations 05/26/2021
RES-DE-REB-2021-3 Fracture Analysis of Vessels – Oak Ridge FAVOR v20.1.12 Theory and Implementation of Algorithms, Methods, and Correlations 06/30/2021
RES-DE-REB-2021-4 Fracture Analysis of Vessels – Oak Ridge FAVOR v20.1.12 User’s Guide 07/15/2021
RES-DE-REB-2021-5 FAVOR Software Quality Assurance Plan (SQAP) 06/21/2021
RES-DE-REB-2021-6 FAVOR Configuration Management and Maintenance Plan (CMMP) 06/21/2021
RES-DE-REB-2021-7 Benchmarking of Probabilistic Fracture Mechanics Models in Grizzly 06/30/2021
RES-DE-REB-2021-8 Assessment of Graphite Properties and Degradation Including Source Dependence 08/31/2021
RES-DE-REB-2021-9 Probabilistic Leak-Before-Break Evaluation of Westinghouse Four-Loop Pressurized-Water Reactor Primary Coolant Loop Piping using the Extremely Low Probability of Rupture Code 08/13/2021
RES-DE-REB-2021-10 FAVOR v20.1.12 Software Requirements Document 09/01/2021
RES-DE-REB-2021-12 Assessment of Cold Spray Technology for Nuclear Power Applications 09/30/2021
RES-DE-REB-2021-13 Summary of Investigations into Addressing the Shallow Surface-Breaking Flaw Issue: Summary and Recommendations 12/31/2021
RES-DE-REB-2021-14-R1 Probabilistic Leak-Before-Break Evaluations of Pressurized-Water Reactor Piping Systems using the Extremely Low Probability of Rupture Code 04/01/2022
RES-DE-REB-2021-15 Application of Probabilistic Analysis Techniques in Mechanical Integrity Assessments 09/24/2021
RES-DE-REB-2021-16 Probabilistic Fracture Mechanics Application: FAVOR Case Study 09/30/2021
RES-DE-REB-2021-17 Technical Challenges and Gaps in Digital-Twin-Enabling Technologies for Nuclear Reactor Application 12/31/2021
RES-DE-CIB-2021-1 Estimation Scheme for Weld Residual Stress Effect on Crack Opening Displacements 03/23/2021
RES-DE-CIB-2021-2 Effect of Crack Face Pressure Distribution on Crack Opening Displacements and Associated Leak Rates 09/18/2020
RES-DE-CIB-2021-3 Technical Assessment of Materials Compatibility in Molten Salt Reactors 03/31/2021
RES-DE-CIB-2021-4 Corrosion in Gas-cooled Reactors 03/31/2021
RES-DE-CIB-2021-5 Status of Advanced Non-Light Water Reactor Research Activities: Materials, Chemistry, and Component Integrity 04/01/2021
RES-DE-CIB-2021-6 Technical Assistance to Review American Society of Mechanical Engineer’s Boiler and Pressure Vessel Code Case and Licensee Relief Requests for Carbon Fiber Repairs 05/18/2021
RES-DE-CIB-2021-7 Corrosion in Sodium Fast Reactors 05/31/2021
RES-DE-CIB-2021-8 Calculational Methods for Reactor Pressure Vessel Fluence in Extended Beltline Locations 05/25/2021
RES-DE-CIB-2021-9 Reactor Pressure Vessel Fluence, DPA, and Uncertainty Quantification in Extended Beltline Locations 05/25/2021
RES-DE-CIB-2021-10 Additional Technical Information in Support of the U.S. Nuclear Regulatory Commission Review of the 2017 Edition of ASME Section III, Division 5, "High Temperature Reactors," Subsection HH, Subpart A: "Graphite Materials." 05/31/2021
RES-DE-CIB-2021-11 Sensitivity Studies and Analyses Involving the Extremely Low Probability of Rupture Code 05/14/2021

To top of page

Page Last Reviewed/Updated Wednesday, February 14, 2024