Published 2017
| Version v1
Journal article
Feasibility of a Breed-and-Burn Molten Salt Reactor
- 1. University of California, Berkeley, Department of Nuclear Engineering, Berkeley, CA 94720-1730 USA (United States)
Description
This work addresses the feasibility and characteristics of the breed and burn (B and B) cycle for Molten Salt Reactors. In the general B and B cycle, natural Uranium or Thorium is used as fuel for a reactor which breeds a sufficient amount to maintain criticality at equilibrium without reprocessing. Interest in applying this scheme to an MSR has developed recently For the MSR B and B scheme considered here, fresh salt containing fertile material is continually fed into the core while salt with the composition of the homogeneous fuel is expelled without reprocessing. Through an analysis of the equilibrium conditions and startup requirements, the feasibility of such a cycle operating with various salts is assessed
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 1174-1176
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52090734
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CRITICALITY; EQUILIBRIUM; FERTILE MATERIALS; MOLTEN SALT REACTORS; NATURAL URANIUM; NUCLEAR FUELS; REPROCESSING; SALTS; THORIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; URANIUM
Optional Information
- Notes
- 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)