Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods

Mariani, Robert Dominick

Title: Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods

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Abstract

Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350.degree. C. to 750.degree. C., and a second additive having a solubility in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350.degree. C. to 750.degree. C. and a solubility of the second additive in the first additive over the temperature range extending from 350.degree. C. to 750.degree. C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

Inventors:: Mariani, Robert Dominick

Issue Date:: 2014-09-09

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1156951

Patent Number(s):: 8831166

Application Number:: 13/021,480

Assignee:: Battelle Energy Alliance, LLC (Idaho Falls, ID)

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

B - PERFORMING OPERATIONS B22 - CASTING B22F - WORKING METALLIC POWDER

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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

B - PERFORMING OPERATIONS B22 - CASTING B22F - WORKING METALLIC POWDER
B22F3/12 - Both compacting and sintering

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G21C3/07 - characterised by their material, e.g. alloys

C - CHEMISTRY C22 - METALLURGY C22C - ALLOYS
C22C1/0458 - {Alloys based on titanium, zirconium, hafnium}
C22C16/00 - Alloys based on zirconium

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DOE Contract Number:: AC07-05ID14517

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats


                    Mariani, Robert Dominick. Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods.  United States: N. p., 2014. 
        Web.

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                    Mariani, Robert Dominick. Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods.  United States.

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                    Mariani, Robert Dominick. Tue .  
        "Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods".  United States.  https://www.osti.gov/servlets/purl/1156951.

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@article{osti_1156951,

  title        = {Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods},

  author       = {Mariani, Robert Dominick},

  abstractNote = {Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350.degree. C. to 750.degree. C., and a second additive having a solubility in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350.degree. C. to 750.degree. C. and a solubility of the second additive in the first additive over the temperature range extending from 350.degree. C. to 750.degree. C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2014},

  month        = {9}

}

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