Molten Salt Reactor Simulations using MPACT-CTF
- Oak Ridge National Laboratory, 1 Bethel Valley Rd. PO Box 2008 MS-6172 Oak Ridge, TN 37831 (United States)
The US Department of Energy and industry have shown significant interest in advanced reactors, as evidenced by over 1.3 billion dollars of private investments in companies to develop advanced reactor concepts. More than seven of these advanced reactor concepts use molten salt reactor (MSR) technology. Based on this interest in MSR technology, ORNL has invested in the development of the MSR simulation capability, extending some capabilities in VERA to model this high-profile reactor concept. In this paper, the MPACT deterministic neutron transport capability and the COBRA Two-Fluid (CTF) subchannel capability are adapted to handle liquid fuel MSRs. Specifically, this work focuses on modifications to the depletion algorithms to account for isotopic mixing, continuous feed, and continuous removal. Models will be added to account for drift of precursors and decay heat emitters as the liquid fuel flows through the reactor coolant system. Modifications to CTF, including the addition of molten salt properties, are also addressed. Finally, the coupled MPACT-CTF capability is used to simulate the 30-year operation of an MSR.
- OSTI ID:
- 23050348
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 116; Conference: 2017 Annual Meeting of the American Nuclear Society, San Francisco, CA (United States), 11-15 Jun 2017; Other Information: Country of input: France; 8 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US); ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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