ML22083A204
| ML22083A204 | |
| Person / Time | |
|---|---|
| Issue date: | 03/15/2022 |
| From: | Kimberly Webber Office of Nuclear Regulatory Research |
| To: | |
| Webber K | |
| References | |
| Download: ML22083A204 (6) | |
Text
NRC Regulatory Research Kim Webber Director, Division of Systems Analysis March 28, 2022
International Experimental Research Studsvik Cladding Integrity Project -IV Framework for Irradiation Experiments SPARE OECD/NEA Program OECD/NEA Program Studsvik Joint Project Generating data and insights on HBU Various joint experiment programs for Saves high-value irradiated fuel fuels during LOCA, storage and aggregating data on cladding creep materials from final waste disposal for transportation behavior and transient behavior, including potential new research through for ATF transports 2019-2024 2021-2024 2020-2025 2021-2023 2021-2024 QUENCH-ATF Halden Reactor Project OECD/NEA Program OECD/NEA Program Experiments for ATF cladding materials in the Opportunities for new insights on key QUENCH facility at Karlsruhe Institute of fuel performance topics from old data Technology (KIT) - Near term chromium-coated cladding under design basis accident (DBA) and beyond DBA 2
We make SAFE use of nuclear technology POSSIBLE.
FFRD Research Research Information Letter (RIL 2021-013)
- Provides NRC technical reviewers with timely interpretations of over 10 years of research on a complex technical issue important to high burnup fuel safety ML21313A145 Source Term (RG 1.183, Rev 1)
- Applicability of Source Term for Accident Tolerant Fuel, High Burn Up and Extended Enrichment, dated May 13, 2020 ML20126G376
- Letter Report on Evaluation of the Impact of Fuel Fragmentation, Relocation, and Dispersal for the Radiological Design Basis Accidents in Regulatory Guide 1.183 ML21197A067 Full-Core LOCA Analysis
- Method to estimate mass loss from FFRD during large break loss of coolant accident (LBLOCA) using NRC tools (Polaris/PARCS - TRACE - FAST) 3 We make SAFE use of nuclear technology POSSIBLE. 3
Fuel Enrichment and Neutronics Research Assessments on Fresh Fuel Criticality ML21040A518
- ATF & Enrichment Impacts to Existing Transportation Packages (ML21040A518) ML21088A254
- ATF & Enrichment Impacts to Fresh Fuel Staging (FY22 Spring)
Assessments on In-Reactor & Spent Nuclear Fuel
- ATF, Enrichment, and HBU Impacts to Decay Heat and ML21088A354 Radiation Source Term (FY22 Spring)
- ATF, Enrichment, and HBU Impacts on Lattice Physics and Fuel Isotopics for BWRs & PWRs (ML21088A336/354/254)
We make SAFE use of nuclear technology POSSIBLE. 4
Severe Accident and Source Term Research Cr-Doped UO2 Fuel
- Not very different from conventional fuels
- Considerable amount of Cr already exists in conventional core
- Some thermophysical properties are slightly less well known
- Limited information regarding fission product speciation and chemistry NUREG/CR-7282 ML21113A277 Cr-Coated Zr-Clad UO2 Fuel
- Not very different from conventional fuels
- Considerable amount of Cr already exists in conventional core
- Some thermophysical properties are slightly less well known
- Initial oxidation expected to be lower HBU/HALEU NUREG/CR-7283
- Thermophysical properties of fuel & cladding ML21210A321
- Fission product chemistry & gap inventories
- Effect of fragmentation on core degradation 5
- No significant differences between HBU/HALEU and HBU We make SAFE use of nuclear technology POSSIBLE. 5
RES Planned Work and Priorities Source Term Calculations Demonstrate capability to for ATF Cr-Coated Cladding perform full-core LOCA using MELCOR simulation to quantify fuel (Sept. 2022) dispersal (FY22/FY23)
Develop in-house Deploy SCALE 6.3 with Assess FAST against Halden familiarity with DOE codes updates to support and SCIP LOCA and (e.g., BISON, Serpent, ATF/HALEU/HBU analyses transient FGR tests Griffin) 6 We make SAFE use of nuclear technology POSSIBLE. 6