Technical Letter Reports – 2021
| Document Number | Title | Publish Date |
|---|---|---|
| Technical Letter Report ANL-13/08 | Leak Rate, Ligament Rupture, and Burst Pressure Model Updates For Allow 690 Thermally-Treated Steam Generator Tubes | 07/24/2021 |
| 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 |
Page Last Reviewed/Updated Friday, July 10, 2026
Page Last Reviewed/Updated Friday, July 10, 2026