ML22083A030

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March 2022 Joint EPRI-INL ATF Workshop - NRC Code Development and Assessment for Accident Tolerant Fuel
ML22083A030
Person / Time
Issue date: 03/24/2022
From: James Corson
Office of Nuclear Regulatory Research
To:
Corson J
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Download: ML22083A030 (9)


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NRC Code Development and Assessment for Accident Tolerant Fuel Joint EPRI-INL ATF Workshop March 2022 James Corson Reactor Systems Engineer RES/DSA/FSCB

Research Concentrates on 3 Areas

  • Literature Reviews and PIRTs
  • Computer Code Development
  • Experimental Programs

PIRTs Help Focus Our Research

  • Lit reviews identify areas where more information would be useful
  • PIRTs help focus on what is most important /

least understood

  • We have completed:

- Severe accident (2020/2021) and Cr-coated in-reactor (2019) PIRTs

- Lit reviews on in-reactor, storage, and transportation behavior Completed reports can be found on the NRC website:

https://www.nrc.gov/reactors/atf/related-docs.html

We Are Updating Our Codes for ATF

  • SCALE

- SCALE 6.3 will have additional ATF compositions and new dopant properties

  • FAST

- Material properties library (MatLib) makes it easy to add new properties

  • Properties available for FeCrAl, Cr-coating

- Embedded Lua allows users to specify their own properties

  • Useful for proprietary models

We Are Updating Our Codes for ATF

  • TRACE

- Coupling to FAST will allow

  • TRACE to benefit from FAST ATF development
  • FAST to benefit from TRACE thermal-hydraulic models
  • MELCOR

- New generalized oxidation model allows users to model FeCrAl, Cr-coated zirc

  • Validated for FeCrAl against QUENCH-19 experiment

We Are Assessing Our Codes for ATF

  • Assessments are based on available data

- FAST assessment of doped fuel centerline temperature and fission gas release tests (TopFuel 2018)

- MELCOR assessment of FeCrAl oxidation from QUENCH-19 test

- SCALE assessments of

  • ATF/LEU+/HBU on decay heat
  • ATF/LEU+ on fresh fuel storage

We Participate in Experimental Programs

  • NRC collaborates with domestic and international partners

- Meetings with DOE and national laboratories

- International research programs

  • Experiments will

- Help improve understanding of ATF behavior

- Provide data for code development and assessment

We Participate in International Research

  • QUENCH-ATF

- Design basis and beyond design basis tests on bundle with Cr-coated cladding

  • Framework for Irradiation Experiments (FIDES)

- Reactivity-initiated accident tests on ATF samples

- Cr-coated cladding creep tests

  • Studsvik Cladding Integrity Project (SCIP-IV)

- Some tests on additive fuels

  • NEA Working Group on Fuel Safety

- Led development of Technical Opinion Paper on ATF

PIRTs, Codes, Experiments are Inter-Related Experiments Importance, Computer Knowledge PIRTs Codes Development Priorities