Published September 1, 2007 | Version v1
Miscellaneous

Thermal- and Fast-Spectrum Molten Salt Reactors for Actinide Burning and Fuel Production

  • 1. Oak Ridge National Lab., Oak Ridge, TN (United States)

Description

In a molten salt reactor (MSR), the fuel is dissolved in a fluoride salt coolant. The technology was partly developed in the 1950s and 1960s. With changing goals for advanced reactors and new technologies, there is currently a renewed interest in MSRs. The new technologies include (1) Brayton power cycles (rather than steam cycles) that eliminate many of the historical challenges in building MSRs and (2) the conceptual development of several fast-spectrum MSRs that have large negative temperature and void coefficients, a unique safety characteristic not found in solid-fuel fast reactors. Earlier MSRs were thermal-neutron-spectrum reactors. Compared with solid-fueled reactors, MSR systems have lower fissile inventories, no radiation damage constraint on attainable fuel burnup, no spent nuclear fuel, no requirement to fabricate and handle solid fuel, and a single isotopic composition of fuel in the reactor. These and other characteristics may enable MSRs to have potentially unique capabilities and competitive economics for actinide burning and extending fuel resources. The status, unique characteristics, and recent worldwide advances in MSRs are described

Availability note (English)

Available from Oak Ridge National Laboratory (US)

Additional details

Publishing Information

Imprint Pagination
vp.

Conference

Title
Advanced Nuclear Fuel Cycles and Systems
Acronym
GLOBAL'07
Dates
9-13 Sep 2007
Place
Boise, ID (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
40013731
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACTINIDES; FAST REACTORS; MOLTEN SALT REACTORS; NUCLEAR FUELS; SOLID FUELS; VOID COEFFICIENT
Descriptors DEC
ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; MATERIALS; METALS; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS

Optional Information

Contract/Grant/Project number
AF3620800; NEAF265; AC05-00OR22725
Funding organization
NE USDOE - Office of Nuclear Energy (United States)
Secondary number(s)
ORNL/PTS--7285