ML22083A204: Difference between revisions

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{{#Wiki_filter:NRC Regulatory Research Kim Webber Director, Division of Systems Analysis March 28, 2022
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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)
ML21088A336 4
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}}

Latest revision as of 13:43, 18 November 2024

Presentation on NRC Regulatory Research - Enabling Regulatory Readiness for Accident Tolerant Fuel, March 22, 2022
ML22083A204
Person / Time
Issue date: 03/15/2022
From: Kimberly Webber
Office of Nuclear Regulatory Research
To:
Webber K
References
Download: ML22083A204 (6)
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