ML19204A285
| ML19204A285 | |
| Person / Time | |
|---|---|
| Issue date: | 08/16/2019 |
| From: | Wendy Reed Division of Spent Fuel Management |
| To: | Advisory Committee on Reactor Safeguards |
| Reed W | |
| Shared Package | |
| ML19204A282 | List: |
| References | |
| NUREG-2224 | |
| Download: ML19204A285 (131) | |
Text
Code of Federal Regulations
Code of Federal Regulations
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Code of Federal Regulations
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Code of Federal Regulations
- 1. deformation caused by creep will proceed slowly over time and will decrease the rod pressure, 2. the decreasing cladding temperature also decreases the hoop stress, and this too will slow the creep rate so that during later stages of dry storage, further creep deformation will become exceedingly small, and 3. in the unlikely event that a breach of the cladding due to creep occurs, it is believed that this will not result in gross rupture.
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- Code of Federal Regulations
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2.3.4.1 Two Alternatives for Calculating Cladding Stress and Strain During Drop Accidents
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- 2.3.5.1 Use of Static Test Results to Evaluate Safety Margins in an HAC Side Drop Event
2.3.5.2 Dynamic Response of a Fuel Rod 2.3.5.3 Seismic Response of a Fuel Rod 2.3.5.4 Thermal Cycling during Loading Operations )
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2.4.3.1 Seismic Events 2.4.3.2 Thermal Cycling during Loading Operations Code of Federal Regulations
- Bounding Release Fractions for High Burnup Spent Nuclear Fuel
3.2.4.1 Supplemental Results from Confirmatory Demonstration 3.2.4.1.1 Initial Licensing or Certification 3.2.4.1.2 Renewal Applications 3.2.4.2 Supplemental Safety Analyses *
- 3.2.4.2.1 Materials and Structural 3.2.4.2.2 Confinement 3.2.4.2.3 Thermal
3.2.4.2.4 Criticality 3.2.4.2.5 Shielding
Code of Federal Regulations
- Bounding Release Fractions for High Burnup Fuel
4.2.4.1 Supplemental Data from Confirmatory Demonstration 4.2.4.2 Supplemental Safety Analyses
- 4.2.4.2.1 Materials and Structural 4.2.4.2.2 Containment 4.2.4.2.3 Thermal 4.2.4.2.4 Criticality
4.2.4.2.5 Shielding
Code of Federal Regulations
J. ASTM Intl.
Metallurgical and Materials Transactions ADuctile-to-Brittle Transition Temperature for High-Burnup Zircaloy-4 and ZIRLOŽ Cladding Alloys Exposed to Simulated Drying-Storage ConditionsEmbrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Effects of Multiple Drying Cycles on High-Burnup PWR Cladding AlloysEffects of Lower Drying-Storage Temperatures on the DBTT of High-Burnup PWR Cladding Alloys Nuclear TechnologyPackaging, Transport, Storage & Security of Radioactive Material International Conference on Management of Spent Fuel from Nuclear Power Reactors: An Integrated Approach to the Back-End of the Fuel CycleZirconium in the Nuclear Industry: 11 th Intl. Symp.
J. Nucl. Mater.End-of-Life Rod Internal Presures in Spent Pressurized Water Reactor FuelZirconium in the Nuclear Industry: 12 th Intl. Symp.
J Strain Analysis for Engineering Design. Proceedings of the Technical Committee Meeting IAEA on Advances in Fuel Technology.J. Nucl. Mater.Nuclear Engineering and Design