ML24151A199
| ML24151A199 | |
| Person / Time | |
|---|---|
| Issue date: | 06/05/2024 |
| From: | Lucas Kyriazidis NRC/RES/DSA/FSCB |
| To: | |
| Lucas Kyriazidis 301-415-7834 | |
| References | |
| Download: ML24151A199 (11) | |
Text
NRC Regulatory Applications with SCALE 2024 SCALEs Users Group June 5th 2024 Lucas Kyriazidis Office of Nuclear Regulatory Research Division of Systems Analysis Fuels & Source Term Code Development 1
NRCs Simulation Codes in the Regulatory Framework 2
SCALE Development & Validation SCALE supports licensing activities in both the Offices of Nuclear Regulatory Regulation (NRR) & Nuclear Materials Safety and Safeguards (NMSS)
Spent fuel pool criticality Generating nuclear physics and decay heat parameters for design basis accident analysis Review of consolidated interim storage facilities Burnup credit analyses NRC participates in multi-lateral experimental programs to validate and assess our computer codes. Recently, NRC has joined Studsviks LAGER program aimed at producing radiochemical isotopic assay data of gadolinia doped fuel rods.
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SCALE Code Development Activities & Priorities NRC actively supports development of SCALE & PARCS, focused around several key areas 1)
Expanding current code capabilities 2)
Assessing current and new LWR & non-LWR concepts 3)
Expanding SCALEs validation & assessment suite 4)
Training & improving the users experience SCALE Assessing SCALE with new experimental data from multi-lateral programs (e.g.,
REGAL, LAGER, EPRI/SKB, etc.)
Improving simulation capabilities of Polaris / PARCS for BWRs Generating new experimental data for expanding the RCA validation basis for HBU & ATF Designs Continued capability & assessment of ATF/HBU/EE, HALEU, non-LWRs Longer-term ATF concepts Higher enrichments, 19.75 wt.% U235 MSRs, SFRs, HTGRs, FHRs, HPRs PARCS Additional assessment of Polaris / PARCS for modern BWR cores Continued capability & assessment for ATF/HBU/EE, HALEU, and non-LWR analysis SFR thermal expansion (radial/axial)
Improve and test hybrid depletion (macro/micro)
Implement new cross-section interpolation scheme for better accuracy at cold conditions PATHS bypass and water rod flow model - for later cross section co-branching on bypass/water rod properties 2X2 PWR depletion sub-node mesh to support ATF; consolidate nodal methods onto 2G-MG CMFD for improved stability FY24 & FY25 Priorities & Highlights Heat Pipe Reactor SCALE Model from NRCs Source Term Demonstration Project 4
Use of SCALE for LWR Regulatory Decision-making Accident Tolerant, High Burnup, and Extended Enrichment Fuels Front-End (Criticality Safety)
In-Reactor & Power Production Shielding, Dose, Inventory Generation, and Decay Heat Numerous publicly-available, technical assessments and reports, using SCALE, for key regulatory areas.
NRC Staff Guidance & Tools Draft 5
Use of SCALE for LWR Regulatory Decision-making Technical assessments supported NMSS review of several increased enrichment transportation package licensing submittals (e.g., DN30-X, RAJ-II, Traveller, etc.)
Commercial LWR fuel vendors are pursuing changes to current enrichment limits of 5 wt. %.
Technical assessment performed to study how increased enrichment impacts currently licensed transportation packages. (SCALE/KENO-VI)
Key quantities of interest were looked at, related to criticality safety.
VersaPac with TRISO pebbles DN30-X with increased U-235 enrichment Traveller with 17x17 PWR fuel assemblies.
CHU-OP-TU package with powdered UO2.
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Use of SCALE for Non-LWR Regulatory Decision-making NRCs Demonstration Projects Highlighting Non-LWR Simulation Capabilities Volume 3 - SCALE/MELCOR Source Term Demonstration Project & Volume 5 - SCALE/MELCOR Fuel Cycle Demonstration Project Validation & Assessment 7
Use of SCALE for Non-LWR Regulatory Decision-making Fluoride Salt Cooled Pebble Bed Reactor MELCOR Model SCALE Analyses to Support Kairos Hermes I Construction Permit Review Leveraged the existing SCALE/MELCOR UCB Mark 1 Reference plant model from Volume 3 to build the SCALE Hermes I model Shutdown control elements not modelled due to SCALE limitations.
Reactor kinetics, power distributions, decay heat, and isotopic fission product inventories calculated in SCALE for use in MELCOR.
SCALE outputs used within MELCOR to model several accidents (insertion of excess reactivity & loss of forced circulation)
Future FY24 SCALE Capability Underway In-Pebble Bed Control Element Modeling in SCALE/TRITON Total Flux 8
Ongoing SCALE/PARCS Development & Research
- Significant efforts underway expanding & assessing SCALE/PARCS capabilities for LWR & non-LWR Upcoming SCALE/MELCOR MSR Fuel Cycle Workshop - July 11th 2024 Workshop will highlight generating MSR inventories in TRITON, performing 3D shielding analyses, and the coupling of ORIGEN to MELCOR for transient analysis (Agenda & Scheduler)
Efforts underway to perform additional detailed assessments of Polaris/PARCS for BWRs Possibly expand and add new data to the existing RCA validation basis for HBU & ATF designs Builds upon recently completed efforts (North Anna PWR samples) documented in Analytical Report for NRC HBU Fuel Specimens Continued capability & assessment of ATF/HBU/EE, HALEU, non-LWRs Expanding SCALE / PARCS capabilities for SFRs (e.g., modeling thermal expansion) 9
For More Information For questions or comments about material in this presentation, please contact Lucas Kyriazidis & Dr. Andrew Bielen in the NRC Office of Nuclear Regulatory Research, within the Fuel and Source Term Code Development Branch at Lucas.Kyriazidis@nrc.gov & Andrew.Bielen@nrc.gov.
For selected list of publications, please visit the following websites:
Non-LWR Fuel Cycle Demonstration Project Non-LWR Source Term Demonstration Project NRC Documents on ATF/HBU/EE 10
References LWRs - ATF/HBU/EE Assessment of Existing Transportation Packages (ML21040A518)
Isotopic and Fuel Lattice Parameter Trends in EE and HBU LWR Fuels (PWR - ML21088A336) (BWR - ML21088A354)
Extended-Enrichment ATF LWR Fuel Isotopic and Lattice Parameter Trends (ML21088A254)
Impacts of LEU+ and ATF on Fresh Fuel Storage Criticality Safety (ML22098A137)
Impacts of LEU+ and HBU Fuel on Decay Heat and Radiation Source Term (ML22159A191)
Pressurized Water Reactor Gadolinia Pin Location Optimization Study (ML24069A006)
Assessment of Core Physics Characteristics of EE and HBU LWR Fuels using Polaris/PARCS Two-Step Approach (PWR - ML23012A122) (BWR - ML23279A041)
Draft - NUREG-2266, Environmental Evaluation of ATF with IE and Higher Burnup Levels (ML23240A756)
NUREG/CR-7284 - SCALE 6.2 Lattice Physics Performance assessment (ML23076A034)
NUREG/CR-7302 Revision 1 - Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses (ML24031A600)
NUREG/CR-7303 - Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses - Nuclide Compositions Prediction with Extended Validation Basis (ML23254A400)
NUREG/CR-7306 - Fuel Assembly and Irradiation Parametric Study for Extended-Enrichment and High-Burnup Light-Water Reactor Spent Nuclear Fuel in Dry Storage Casks and Transportation Packages (ML24114A120)
NUREG/CR-TBD - Validation Studies for HBU and EE Fuels in BUC Criticality Safety Analyses (Coming Later in 2024)
NUREG/CR-TBD - Sensitivity / Uncertainty Methods for Nuclear Criticality Safety Validation (Coming Later in 2024)
Non-LWRs - Volume 3 Heat Pipe Reactors (Workshop slides, SCALE Report, MELCOR Report)
High-temperature gas-cooled reactor (Workshop slides, SCALE Report, MELCOR Report)
Fluoride-salt-cooled high-temperature reactor (Workshop slides, SCALE Report, MELCOR Report)
Molten-salt-fueled reactor (Workshop slides, SCALE Report, MELCOR Report)
Sodium-cooled fast reactor (Workshop slides, SCALE Report, MELCOR Report)
SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs (ML2414A078)
Non-LWRs - Volume 5 Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration (ML24004A270)
SFRs (Workshop slides, SCALE Report)
HTGRs (Workshop slides)
Links to the reports mentioned in this presentation, tabulated below 11