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
We make SAFE use of nuclear technology POSSIBLE.
International Experimental Research 2019-2024 Studsvik Cladding Integrity Project -IV OECD/NEA Program Generating data and insights on HBU fuels during LOCA, storage and transportation 2021-2023 Halden Reactor Project OECD/NEA Program Opportunities for new insights on key fuel performance topics from old data 2021-2024 Framework for Irradiation Experiments OECD/NEA Program Various joint experiment programs for aggregating data on cladding creep behavior and transient behavior, including for ATF 2021-2024 QUENCH-ATF OECD/NEA Program Experiments for ATF cladding materials in the QUENCH facility at Karlsruhe Institute of Technology (KIT) - Near term chromium-coated cladding under design basis accident (DBA) and beyond DBA 2020-2025 SPARE Studsvik Joint Project Saves high-value irradiated fuel materials from final waste disposal for potential new research through transports 2
We make SAFE use of nuclear technology POSSIBLE.
FFRD Research 3
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.
ML21040A518 Fuel Enrichment and Neutronics Research 4
Assessments on Fresh Fuel Criticality ATF & Enrichment Impacts to Existing Transportation Packages (ML21040A518)
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 Radiation Source Term (FY22 Spring)
ATF, Enrichment, and HBU Impacts on Lattice Physics and Fuel Isotopics for BWRs & PWRs (ML21088A336/354/254)
ML21088A336 ML21088A354 ML21088A254 4
We make SAFE use of nuclear technology POSSIBLE.
Severe Accident and Source Term Research 5
HBU/HALEU
- Thermophysical properties of fuel & cladding
- Fission product chemistry & gap inventories
- Effect of fragmentation on core degradation
- No significant differences between HBU/HALEU and HBU NUREG/CR-7282 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 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-7283 ML21113A277 ML21210A321 5
We make SAFE use of nuclear technology POSSIBLE.
RES Planned Work and Priorities 6
Demonstrate capability to perform full-core LOCA simulation to quantify fuel dispersal (FY22/FY23)
Source Term Calculations for ATF Cr-Coated Cladding using MELCOR (Sept. 2022)
Deploy SCALE 6.3 with updates to support ATF/HALEU/HBU analyses Develop in-house familiarity with DOE codes (e.g., BISON, Serpent, Griffin)
Assess FAST against Halden and SCIP LOCA and transient FGR tests 6