Transient Thermal Response of the Pb-AHTR to Loss of Forced Cooling
- Department of Nuclear Engineering, University of California, Berkeley, CA 94720-1730 (United States)
- Idaho National Laboratory, Idaho Falls, ID 83415-3890 (United States)
In liquid-salt cooled high temperature reactors, such as the Pebble Bed Advanced High Temperature Reactor (PB-AHTR), natural circulation of the liquid salt provides the primary decay heat removal mechanism during transients such as the loss of forced cooling (LOFC) transient. Because this natural circulation is highly effective, for LOFC the temperature differences across the core of the PB-AHTR are much lower than in modular helium reactors (MHR), where decay heat removal occurs primarily by thermal radiation and conduction. This allows the PB-AHTR to operate with much higher power density than a comparable MHR, which in turn provides the potential for attractive economics. This paper reports RELAP5-3D simulations for the PB-AHTR that verify its excellent response to LOFC transients. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 20979643
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 13 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
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