Preliminary neutronic assessment of a novel fluoride-salt-cooled high-temperature reactor design
- University of Massachusetts Lowell, 1 University Ave, Lowell, MA, 01854 (United States)
The Fluoride-Salt-Cooled High-Temperature Reactor (FHR) is a molten salt cooled, graphite moderated high temperature reactor. In this work, single-batch cycle length, block power distributions, and temperature-related reactivity effects were assessed using the SCALE code suite. Two types of parametric studies were performed. The first consisted of fixed temperature (isothermal) cases in which to determine the relationship between operation power and cycle length as well as pin power distributions. This second study calculates various isothermal reactivity coefficients based on heterogeneous temperature distributions. Reactivity coefficients with respect to the temperature of the fuel, coolant, and moderator were performed separately to determine their individual contributions. (authors)
- OSTI ID:
- 23042804
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 115; Conference: 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV (United States), 6-10 Nov 2016; Other Information: Country of input: France; 5 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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