ML22140A337

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Iyengarr-hv-w19
ML22140A337
Person / Time
Issue date: 03/08/2022
From: Carlson J, Raj Iyengar, Ricardo Torres
Office of Nuclear Regulatory Research, Pacific Northwest National Laboratory
To:
Office of Nuclear Reactor Regulation
References
Download: ML22140A337 (7)


Text

Technical Considerations for the Molten Salt Reactor Fuel Cycle J. Carlson, R. Torres*, and R. Iyengar Reactor Engineering Branch Division of Engineering Office of Nuclear Regulatory Research

  • now with Pacific Northwest National Laboratory, Richland, WA

Prior Operating Experience Aircraft Reactor Experiment (1954)

Molten Salt Reactor Experiment (MSRE)

(19651969)

  • Two molten salt reactor (MSR) experiments operated by Oak Ridge National Laboratory
  • Prior front-end activities performed at Y-12 National Security Complex
  • Lessons-learned from MSRE decommissioning
  • No NRC regulatory precedent for front-and back-end activities for MSRs
  • Fuel salt enrichment, production, blending o Chemical reactivity hazards of halide salts o Production of uranium and thorium fuel salts from source material
  • Transportation packages designed to support offsite operations o Moderator inclusion/criticality o Containment performance Front-End Considerations

(Riley et al., 2018)

MSR Waste Streams

  • Confinement materials compatibility/performance
  • Dose management

radiolysis from beta/gamma radiation

  • Graphite waste management FuelDrainTanks/FuelFlush TankinMSREDrainTankCell Back-End Considerations DrySpentFuelCasksonConcrete PadatNuclearPowerPlantSite

MSRs pose unique challenges for front-end and back-end operations MSRs pose unique challenges for front-end and back-end operations RES and NMSS are collaborating on establishing future activities to ensure readiness for licensing and certification reviews RES and NMSS are collaborating on establishing future activities to ensure readiness for licensing and certification reviews Continued/expanded engagement with the DOE and industry will support mutual understanding of technical and regulatory information needs Continued/expanded engagement with the DOE and industry will support mutual understanding of technical and regulatory information needs Summary

  • Rosenthal, M.W. An Account of Oak Ridge National Laboratorys Thirteen Nuclear Reactors, Report No. ORNL/TM-2009/181. Oak Ridge, TN: Oak Ridge National Laboratory. 2010.
  • Fredrickson, G., G. Cao, R, Gakhar, and T. Yoo. Molten Salt Reactor Salt ProcessingTechnology Status, Report No. INL/EXT-18-51033.

Idaho Falls, ID: Idaho National Laboratory. 2018.

  • Riley, B.J., et al. Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors, Report No. PNNL-27723.

Richland, WA: Pacific Northwest National Laboratory. 2018.

References