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)