Evaluation of the Molten Salt Breeder Reactor

None, None

doi:10.2172/4372873

Title: Evaluation of the Molten Salt Breeder Reactor

Full Record
Other Related Research

Abstract

Topics discussed concerning the molten salt breeder reactor program include: resource utilization; historical development of molten salt reactors; molten salt breeder reactor concept description; status of molten salt breeder reactor technology; and industrial participation in the molten salt breeder reactor program. (17 references) (DCC)

Publication Date:: 1972-09-01

Research Org.:: USAEC Division of Reactor Development and Technology, Washington, D.C. (United States)

Sponsoring Org.:: US Atomic Energy Commission (AEC); Federal Council on Science and Technology R&D Goals Study

OSTI Identifier:: 4372873

Report Number(s):: WASH-1222

NSA Number:: NSA-29-009373

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; *BREEDER REACTORS- DESIGN; *MOLTEN SALT COOLED REACTORS- DESIGN; *MOLTEN SALT FUELED REACTORS- DESIGN; ECONOMICS; EFFICIENCY; REACTOR MAINTENANCE; REACTOR MATERIALS; REACTOR OPERATION; REACTOR SAFETY; SPECIFICATIONS

Citation Formats


                    None, None. Evaluation of the Molten Salt Breeder Reactor.  United States: N. p., 1972. 
        Web.  doi:10.2172/4372873.

Copy to clipboard


                    None, None. Evaluation of the Molten Salt Breeder Reactor.  United States.  https://doi.org/10.2172/4372873

Copy to clipboard


                    None, None. 1972.  
        "Evaluation of the Molten Salt Breeder Reactor".  United States.  https://doi.org/10.2172/4372873.  https://www.osti.gov/servlets/purl/4372873.

Copy to clipboard


                    
@article{osti_4372873,

  title        = {Evaluation of the Molten Salt Breeder Reactor},

  author       = {None, None},

  abstractNote = {Topics discussed concerning the molten salt breeder reactor program include: resource utilization; historical development of molten salt reactors; molten salt breeder reactor concept description; status of molten salt breeder reactor technology; and industrial participation in the molten salt breeder reactor program. (17 references) (DCC)},

  doi          = {10.2172/4372873},

  url          = {https://www.osti.gov/biblio/4372873},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1972},

  month        = {9}

}

Copy to clipboard

Technical Report:

View Technical Report (8.72 MB)

https://doi.org/10.2172/4372873

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

Molten Salt Reactor Signatures and Modeling Study

Technical Report Dion, Michael; Worrall, Louise; Croft, Stephen; ...

Molten salt reactor (MSR) technologies, either liquid fueled and cooled or only liquid cooled, pose specific, unique challenges for safeguards of the special nuclear material during the operation, fueling, and maintenance of the reactor. MSRs are one type of Generation IV technologies being invested in and considered for U.S. domestic fabrication primarily for electricity and process heat production. These designs have generated growing commercial interest for several reasons, including high (≈40%) thermal efficiency, ease of fueling, improved use of uranium fuel, potential utilization of thorium fuel, and proposed inherent safety features. U.S. companies have several planned designs that differ inmore »« less
https://doi.org/10.2172/1761616

Full Text Available
Material Control & Accountancy for Molten Salt Reactors (FY2021 Report)

Technical Report Dion, Michael; Greenwood, Michael; Hogue, Karen; ...

There is significant domestic and international interest, investment, and research and development momentum to pursue advanced nuclear reactor technologies. Molten salt reactor (MSR) concepts display the largest variability in fuel type and design features among the current advanced concepts. MSRs have been proposed with various core designs, sizes (power), and fuel cycles. Salt-fueled molten salt systems represent the only advanced reactor type with fuel that is not in a solid form during operation. These “liquid-fueled” MSRs are unique from perspectives of fuel fabrication, spent irradiated fuel and waste components, licensing, and material control and accountability (MC&A) including the potential ofmore »« less
https://doi.org/10.2172/1840163

Full Text Available
Dynamic Analysis of the Next Generation Molten-Salt Breeder Reactor System

Journal Article Chvala, O.; Lish, M.; Singh, V.; ... - Transactions of the American Nuclear Society

The conceptual design of a 1000 MWe two-fluid molten-salt breeder reactor (MSBR) station was performed during 1966-1970 at Oak Ridge National Laboratory (ORNL) with the goal of using the U-233 fuel cycle. This modular design with four reactor modules has an electrical output of 250 MW/module. The abundance of Th-232 was attractive in converting it to U-233 in a thermal breeder reactor. The two-fluid reactor is graphite-moderated 'with a {sup 7}LiF-BeF{sub 2}-UF{sub 4} fuel salt circulated through the core and a {sup 7}LiF-ThF{sub 4}-BeF{sub 2} blanket salt circulated through separate flow channels distributed throughout the core, as well as inmore »« less
Fast Spectrum Molten Salt Reactor Options

Technical Report Gehin, Jess; Holcomb, David; Flanagan, George; ...

During 2010, fast-spectrum molten-salt reactors (FS-MSRs) were selected as a transformational reactor concept for light-water reactor (LWR)-derived heavy actinide disposition by the Department of Energy-Nuclear Energy Advanced Reactor Concepts (ARC) program and were the subject of a preliminary scoping investigation. Much of the reactor description information presented in this report derives from the preliminary studies performed for the ARC project. This report, however, has a somewhat broader scope-providing a conceptual overview of the characteristics and design options for FS-MSRs. It does not present in-depth evaluation of any FS-MSR particular characteristic, but instead provides an overview of all of the majormore »« less
https://doi.org/10.2172/1018987

Full Text Available
Liquid fuel molten salt reactors for thorium utilization

Journal Article Gehin, Jess; Powers, Jeffrey - Nuclear Technology

Molten salt reactors (MSRs) represent a class of reactors that use liquid salt, usually fluoride- or chloride-based, as either a coolant with a solid fuel (such as fluoride salt-cooled high temperature reactors) or as a combined coolant and fuel with fuel dissolved in a carrier salt. For liquid-fuelled MSRs, the salt can be processed online or in a batch mode to allow for removal of fission products as well as introduction of fissile fuel and fertile materials during reactor operation. The MSR is most commonly associated with the ²³³U/thorium fuel cycle, as the nuclear properties of ²³³U combined with themore »« less
Cited by 15
https://doi.org/10.13182/NT15-124

Full Text Available

Similar Records