Container for reprocessing and permanent storage of spent nuclear fuel assemblies

Forsberg, Charles W

Title: Container for reprocessing and permanent storage of spent nuclear fuel assemblies

Abstract

A single canister process container for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining their integrity at temperature necessary to oxide the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container.

Inventors:

Forsberg, Charles W ^[1]

Oak Ridge, TN

Issue Date:: 1992-01-01

Research Org.:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 868203

Patent Number(s):: 5098645

Assignee:: United States of America as represented by United States (Washington, DC)

Patent Classifications (CPCs):: G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS

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

Show more

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G21C19/06 - Magazines for holding fuel elements or control elements

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

Show less

DOE Contract Number:: AC05-84OR21400

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: container; reprocessing; permanent; storage; spent; nuclear; fuel; assemblies; single; canister; process; comprising; zirconium-based; cladding; comprises; collapsible; walls; temperature; alloy; array; support; means; capable; withstanding; oxidize; sufficient; ductility; maintain; integrity; collapsed; pressure; maintaining; oxide; introduce; remove; fluids; fuel assemblies; nuclear fuel; spent nuclear; support means; permanent storage; remove fluids; temperature alloy; assemblies comprising; container comprises; /376/250/

Citation Formats


                    Forsberg, Charles W. Container for reprocessing and permanent storage of spent nuclear fuel assemblies.  United States: N. p., 1992. 
        Web.

Copy to clipboard


                    Forsberg, Charles W. Container for reprocessing and permanent storage of spent nuclear fuel assemblies.  United States.

Copy to clipboard


                    Forsberg, Charles W. Wed .  
        "Container for reprocessing and permanent storage of spent nuclear fuel assemblies".  United States.  https://www.osti.gov/servlets/purl/868203.

Copy to clipboard


                    
@article{osti_868203,

  title        = {Container for reprocessing and permanent storage of spent nuclear fuel assemblies},

  author       = {Forsberg, Charles W},

  abstractNote = {A single canister process container for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining their integrity at temperature necessary to oxide the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1992},

  month        = {1}

}

Copy to clipboard

Patent:

Save / Share:

Export Metadata

Save to My Library

Works referenced in this record:

Immobilisation of high level nuclear reactor wastes in SYNROC
journal, March 1979

Ringwood, A. E.; Kesson, S. E.; Ware, N. G.
Nature, Vol. 278, Issue 5701
https://doi.org/10.1038/278219a0

Immobilization of high-level waste in ceramic waste forms
journal, July 1986

Ringwood, Alfred Edward; Kelly, P. M.
Philosophical Transactions of the Royal Society of London. Series A, Mathematical and Physical Sciences, Vol. 319, Issue 1545, p. 63-82
https://doi.org/10.1098/rsta.1986.0086

Uniaxial hot-pressing in bellows containers
journal, January 1983

Ringwood, A. E.; Major, A.; Ramm, E. J.
Nuclear and Chemical Waste Management, Vol. 4, Issue 2
https://doi.org/10.1016/0191-815X(83)90003-7

Similar Records in DOE Patents and OSTI.GOV collections:

Container for reprocessing and permanent storage of spent nuclear fuel assemblies

Patent Forsberg, C W

A single canister process container is described for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining its integrity at a temperature necessary to oxidize the zirconium-based cladding. The process container also has means to introduce andmore » « less
Advanced dry head-end reprocessing of light water reactor spent nuclear fuel

Patent Collins, Emory D; Delcul, Guillermo D; Hunt, Rodney D; ...

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gasmore » « less
Full Text Available
Method for reprocessing and separating spent nuclear fuels

Patent Krikorian, Oscar H [Danville, CA]; Grens, John Z [Livermore, CA]; Parrish, Sr., William H. (Walnut Creek, CA)

Spent nuclear fuels, including actinide fuels, volatile and non-volatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reductionmore » is complete. « less
Full Text Available
Molten tin reprocessing of spent nuclear fuel elements

Patent Heckman, Richard A [Castro Valley, CA]

A method and apparatus for reprocessing spent nuclear fuel is described. Within a containment vessel, a solid plug of tin and nitride precipitates supports a circulating bath of liquid tin therein. Spent nuclear fuel is immersed in the liquid tin under an atmosphere of nitrogen, resulting in the formation of nitride precipitates. The layer of liquid tin and nitride precipitates which interfaces the plug is solidified and integrated with the plug. Part of the plug is melted, removing nitride precipitates from the containment vessel, while a portion of the plug remains solidified to support the liquid tin and nitride precipitatesmore » « less
Full Text Available
Advanced dry head-end reprocessing of light water reactor spent nuclear fuel

Patent Collins, Emory D.; Delcul, Guillermo D.; Hunt, Rodney D.; ...

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gasmore » « less
Full Text Available

Similar Records

Title: Container for reprocessing and permanent storage of spent nuclear fuel assemblies

Abstract

Citation Formats

Immobilisation of high level nuclear reactor wastes in SYNROC journal, March 1979

Immobilization of high-level waste in ceramic waste forms journal, July 1986

Uniaxial hot-pressing in bellows containers journal, January 1983

Immobilisation of high level nuclear reactor wastes in SYNROC
journal, March 1979

Immobilization of high-level waste in ceramic waste forms
journal, July 1986

Uniaxial hot-pressing in bellows containers
journal, January 1983