ML22140A337
| 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
- 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 Aircraft Reactor Molten Salt Reactor Experiment Experiment (MSRE)
(1954) (19651969)
Front-End Considerations
- 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
(Riley et al., 2018)
MSR Waste Streams
Back-End Considerations
- Confinement materials compatibility/performance
- Dose management
- Fluorine gas generation:
radiolysis from beta/gamma radiation
- Graphite waste management Dry Spent Fuel Casks on Concrete Fuel Drain Tanks/Fuel Flush Pad at Nuclear Power Plant Site Tank in MSRE Drain Tank Cell
MSRs pose unique challenges for front-end and back-end operations RES and NMSS are collaborating on establishing future activities to ensure Summary readiness for licensing and certification reviews Continued/expanded engagement with the DOE and industry will support mutual understanding of technical and regulatory information needs
References
- 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.