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Title: Pu-Zr alloy for high-temperature foil-type fuel

Abstract

A nuclear reactor fuel alloy consists essentially of from slightly greater than 7 to about 4 w/o zirconium, balance plutonium, and is characterized in that the alloy is castable and is rollable to thin foils. A preferred embodiment of about 7 w/o zirconium, balance plutonium, has a melting point substantially above the melting point of plutonium, is rollable to foils as thin as 0.0005 inch thick, and is compatible with cladding material when repeatedly cycled to temperatures above 650.degree. C. Neutron reflux densities across a reactor core can be determined with a high-temperature activation-measurement foil which consists of a fuel alloy foil core sandwiched and sealed between two cladding material jackets, the fuel alloy foil core being a 7 w/o zirconium, plutonium foil which is from 0.005 to 0.0005 inch thick.

Inventors:
 [1]
  1. LaGrange, IL
Issue Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
OSTI Identifier:
862961
Patent Number(s):
4059439
Assignee:
United States of America as represented by United States Energy (Washington, DC)
Patent Classifications (CPCs):
C - CHEMISTRY C22 - METALLURGY C22C - ALLOYS
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
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
pu-zr; alloy; high-temperature; foil-type; fuel; nuclear; reactor; consists; essentially; slightly; zirconium; balance; plutonium; characterized; castable; rollable; foils; preferred; embodiment; melting; substantially; 0005; inch; thick; compatible; cladding; material; repeatedly; cycled; temperatures; 650; degree; neutron; reflux; densities; core; determined; activation-measurement; foil; sandwiched; sealed; jackets; 005; inch thick; fuel alloy; nuclear reactor; preferred embodiment; reactor core; reactor fuel; consists essentially; cladding material; activation-measurement foil; flux densities; balance plutonium; alloy consists; pu-zr alloy; temperature activation; high-temperature activation-measurement; type fuel; /420/376/976/

Citation Formats

McCuaig, Franklin D. Pu-Zr alloy for high-temperature foil-type fuel. United States: N. p., 1977. Web.
McCuaig, Franklin D. Pu-Zr alloy for high-temperature foil-type fuel. United States.
McCuaig, Franklin D. Sat . "Pu-Zr alloy for high-temperature foil-type fuel". United States. https://www.osti.gov/servlets/purl/862961.
@article{osti_862961,
title = {Pu-Zr alloy for high-temperature foil-type fuel},
author = {McCuaig, Franklin D},
abstractNote = {A nuclear reactor fuel alloy consists essentially of from slightly greater than 7 to about 4 w/o zirconium, balance plutonium, and is characterized in that the alloy is castable and is rollable to thin foils. A preferred embodiment of about 7 w/o zirconium, balance plutonium, has a melting point substantially above the melting point of plutonium, is rollable to foils as thin as 0.0005 inch thick, and is compatible with cladding material when repeatedly cycled to temperatures above 650.degree. C. Neutron reflux densities across a reactor core can be determined with a high-temperature activation-measurement foil which consists of a fuel alloy foil core sandwiched and sealed between two cladding material jackets, the fuel alloy foil core being a 7 w/o zirconium, plutonium foil which is from 0.005 to 0.0005 inch thick.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1977},
month = {1}
}

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