ML23082A022
| ML23082A022 | |
| Person / Time | |
|---|---|
| Issue date: | 03/22/2023 |
| From: | Chung A NRC/RES/DSA |
| To: | |
| References | |
| Download: ML23082A022 (10) | |
Text
2023 NRC Overview of ATF Research Activities Alice Chung Fuel and Source Term Code Development Branch (FSCB)
Division of System Analysis (DSA)
Nuclear Regulatory Research (RES)
Agenda
- International Research Updates
- Code Development and Analysis Update
- Future Work
NRC Participation in International Research Updates
- QUENCH-ATF
- Benchmark activities on DBA/BDBA tests
- Assessing FAST against LOCA tests from SCIP IV
- Provided feedback on upcoming SCIP V program
- FIDES
- Contributed to P2M benchmark - journal paper to be published in Special Issue of Nuclear Technology
- Participating in HERA benchmark efforts
- NRC interested in potential future RIA and LOCA testing in TREAT
Code Development and Analysis Update
- Material properties library updates and capabilities for new materials
- MELCOR, FAST, SCALE, PARCS
- Ongoing FAST/TRACE coupling
- NRCs Workflow for Holistic Accident Multi-physics methodology (to be discussed on Wed)
- Source term calculation (to be discussed on Wed)
Code Development and Analysis Update
- Recently posted assessments:
- Assessment of Existing Transportation Packages for Use with HALEU (February 2021)
- Extended Enrichment ATF LWR Fuel Isotopic and Lattice Parameter Trends (March 2021)
- Assessment of FAST for Spent Fuel Calculations on HBU and High Enriched Fuel (October 2021)
- Impacts of LEU+ and ATF on Fresh Fuel Storage - Criticality Safety (February 2022)
- Impacts of LEU+ and HBU fuel on Decay heat and Radiation Source Term (April 2022)
- Additional literature reviews and code assessment reports:
https://www.nrc.gov/reactors/power/atf/related-docs.html
Future Work
- Upcoming reports to be issued on:
- Core-level reactor physics assessments
- Transition cycle report on ATF & EE
- HBU/EE for PWRs
- HBU/EE for BWRs
- Back-end Spent Nuclear Fuel assessments
- Burnup credit for EE/HBU fuels
- Phenomena Identification and Ranking Table (PIRT)
- Fuel Dispersal
- Spent Fuel Storage and Transportation for ATF/EE/HBU Fuels
Breaking Down FFRD What are the cladding temperatures as a function of How many rods time through the core? (i.e. not just the hot rod PCT) rupture?
Whats the burnup of each ruptured How much fuel disperses?
rod?
Research has focused on estimating the blue boxes More work needed to address purple boxes What are the consequences of dispersal?
Transport:
Terminal Pressure Chemical velocity of Coolability Dose GSI-191 Pulse Effects buoyancy 7
force
PIRT- Fuel Dispersal
- Objective is to focus on what happens after fuel is released to the coolant and its consequences
- Not to re-evaluate fragmentation or relocation behavior
- Industry has expressed interest in evaluating potential consequences of fuel dispersal
PIRT- Spent Fuel Storage and Transportation
- PIRT in FY24 - focused on the spent fuel storage and transportation of:
- Near-term ATF concepts (Cr-coated Zirconium & FeCrAl claddings) with EE (up to 8 - 10 wt. % U-235), and HBU (up to 75 GWd/MTU rod-average)
- Objective is to focus on materials, structural and thermal degradation, and the failure phenomena for the selected ATF technologies, specific to spent fuel and transportation applications
Questions?