Molten salt fuels with high plutonium solubility

Moir, Ralph W; Turchi, Patrice E.A.; Shaw, Henry F; Kaufman, Larry

Title: Molten salt fuels with high plutonium solubility

Abstract

The present invention includes a composition of LiF--ThF.sub.4--UF.sub.4--PuF.sub.3 for use as a fuel in a nuclear engine.

Inventors:: Moir, Ralph W; Turchi, Patrice E.A.; Shaw, Henry F; Kaufman, Larry

Issue Date:: 2013-08-13

Research Org.:: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1092985

Patent Number(s):: 8506855

Application Number:: 12/888,704

Assignee:: Lawrence Livermore National Security, LLC (Livermore, CA)

Patent Classifications (CPCs):: Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS

Show more

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
Y02E30/30 - Nuclear fission reactors

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G21C3/58 - Solid reactor fuel {Pellets made of fissile material}

Show less

DOE Contract Number:: AC52-07NA27344

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats


                    Moir, Ralph W, Turchi, Patrice E.A., Shaw, Henry F, and Kaufman, Larry. Molten salt fuels with high plutonium solubility.  United States: N. p., 2013. 
        Web.

Copy to clipboard


                    Moir, Ralph W, Turchi, Patrice E.A., Shaw, Henry F, & Kaufman, Larry. Molten salt fuels with high plutonium solubility.  United States.

Copy to clipboard


                    Moir, Ralph W, Turchi, Patrice E.A., Shaw, Henry F, and Kaufman, Larry. Tue .  
        "Molten salt fuels with high plutonium solubility".  United States.  https://www.osti.gov/servlets/purl/1092985.

Copy to clipboard


                    
@article{osti_1092985,

  title        = {Molten salt fuels with high plutonium solubility},

  author       = {Moir, Ralph W and Turchi, Patrice E.A. and Shaw, Henry F and Kaufman, Larry},

  abstractNote = {The present invention includes a composition of LiF--ThF.sub.4--UF.sub.4--PuF.sub.3 for use as a fuel in a nuclear engine.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2013},

  month        = {8}

}

Copy to clipboard

Patent:

Save / Share:

Export Metadata

Save to My Library

Works referenced in this record:

Reactor physic and reprocessing scheme for innovative molten salt reactor system
journal, January 2009

Delpech, S.; Merle-Lucotte, E.; Heuer, D.
Journal of Fluorine Chemistry, Vol. 130, Issue 1
https://doi.org/10.1016/j.jfluchem.2008.07.009

Evaluating physical properties of molten salt reactor fluoride mixtures
journal, January 2009

Khokhlov, Vladimir; Ignatiev, Victor; Afonichkin, Valery
Journal of Fluorine Chemistry, Vol. 130, Issue 1
https://doi.org/10.1016/j.jfluchem.2008.07.018

Neutronic performance of HYLIFE-II fusion reactor using various thorium molten salts
journal, November 2006

Übeyli, Mustafa
Annals of Nuclear Energy, Vol. 33, Issue 17-18
https://doi.org/10.1016/j.anucene.2006.09.006

Molten Salt Fuel Version of Laser Inertial Fusion Fission Energy (LIFE)
journal, August 2009

Moir, R. W.; Shaw, H. F.; Caro, A.
Fusion Science and Technology, Vol. 56, Issue 2
https://doi.org/10.13182/FST18-8166

Similar Records in DOE Patents and OSTI.GOV collections:

Method of removal of heavy metal from molten salt in IFR fuel pyroprocessing

Patent Gay, Eddie C [Park Forest, IL]

An electrochemical method of separating heavy metal values from a radioactive molten salt including Li halide at temperatures of about 500.degree. C. The method comprises positioning a solid Li--Cd alloy anode in the molten salt containing the heavy metal values, positioning a Cd-containing cathode or a solid cathode positioned above a catch crucible in the molten salt to recover the heavy metal values, establishing a voltage drop between the anode and the cathode to deposit material at the cathode to reduce the concentration of heavy metals in the salt, and controlling the deposition rate at the cathode by controlling themore » current between the anode and cathode. « less
Full Text Available
Molten salt extraction of transuranic and reactive fission products from used uranium oxide fuel

Patent Herrmann, Steven Douglas

Used uranium oxide fuel is detoxified by extracting transuranic and reactive fission products into molten salt. By contacting declad and crushed used uranium oxide fuel with a molten halide salt containing a minor fraction of the respective uranium trihalide, transuranic and reactive fission products partition from the fuel to the molten salt phase, while uranium oxide and non-reactive, or noble metal, fission products remain in an insoluble solid phase. The salt is then separated from the fuel via draining and distillation. By this method, the bulk of the decay heat, fission poisoning capacity, and radiotoxicity are removed from the usedmore » « less
Full Text Available
Encapsulation of high temperature molten salts

Patent Oxley, James D.; Mathur, Anoop Kumar

The present disclosure relates to a method of encapsulating microcapsules containing relatively high temperature phase change materials and the microcapsules so produced. The microcapsules are coated with an inorganic binder, film former and an inorganic filler. The microcapsules may include a sacrificial layer that is disposed between the particle and the coating. The microcapsules may also include an inner coating layer, sacrificial layer and outer coating layer. The microcapsules are particularly useful for thermal energy storage in connection with, e.g., heat collected from concentrating solar collectors.
Full Text Available
High durability fuel cell components with cerium salt additives

Patent Frey, Matthew H.; Pierpont, Daniel M.; Hamrock, Steven J.

A fuel cell membrane electrode assembly is provided comprising a polymer electrolyte membrane which comprises a polymer that comprises bound anionic functional groups, wherein the polymer electrolyte membrane additionally comprises cerium cations. In another aspect, a fuel cell membrane electrode assembly is provided comprising a polymer electrolyte membrane which comprises a polymer that comprises bound anionic functional groups, wherein at least a portion of the anionic functional groups are in acid form and at least a portion of the anionic functional groups are neutralized by cerium cations. In another aspect, a polymer electrolyte membrane is provided which comprises a polymermore » « less
Full Text Available
High durability fuel cell components with cerium salt additives

Patent Frey, Matthew H.; Pierpont, Daniel M.; Hamrock, Steven J.

A fuel cell membrane electrode assembly is provided comprising a polymer electrolyte membrane which comprises a polymer that comprises bound anionic functional groups, wherein the polymer electrolyte membrane additionally comprises cerium cations. In another aspect, a fuel cell membrane electrode assembly is provided comprising a polymer electrolyte membrane which comprises a polymer that comprises bound anionic functional groups, wherein at least a portion of the anionic functional groups are in acid form and at least a portion of the anionic functional groups are neutralized by cerium cations. In another aspect, a polymer electrolyte membrane is provided which comprises a polymermore » « less
Full Text Available

Similar Records

Title: Molten salt fuels with high plutonium solubility

Abstract

Citation Formats

Reactor physic and reprocessing scheme for innovative molten salt reactor system journal, January 2009

Evaluating physical properties of molten salt reactor fluoride mixtures journal, January 2009

Neutronic performance of HYLIFE-II fusion reactor using various thorium molten salts journal, November 2006

Molten Salt Fuel Version of Laser Inertial Fusion Fission Energy (LIFE) journal, August 2009

Reactor physic and reprocessing scheme for innovative molten salt reactor system
journal, January 2009

Evaluating physical properties of molten salt reactor fluoride mixtures
journal, January 2009

Neutronic performance of HYLIFE-II fusion reactor using various thorium molten salts
journal, November 2006

Molten Salt Fuel Version of Laser Inertial Fusion Fission Energy (LIFE)
journal, August 2009