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Title: Pu-ZR Alloy high-temperature activation-measurement foil

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 flux 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. Westmont, IL
Issue Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
OSTI Identifier:
862895
Patent Number(s):
4039378
Application Number:
05/735,566
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; activation-measurement; foil; nuclear; reactor; fuel; 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; flux; densities; core; determined; sandwiched; sealed; jackets; 005; inch thick; fuel alloy; nuclear reactor; preferred embodiment; reactor core; neutron flux; reactor fuel; consists essentially; cladding material; activation-measurement foil; flux densities; balance plutonium; alloy consists; pu-zr alloy; temperature activation; high-temperature activation-measurement; /376/250/420/976/

Citation Formats

McCuaig, Franklin D. Pu-ZR Alloy high-temperature activation-measurement foil. United States: N. p., 1977. Web.
McCuaig, Franklin D. Pu-ZR Alloy high-temperature activation-measurement foil. United States.
McCuaig, Franklin D. Tue . "Pu-ZR Alloy high-temperature activation-measurement foil". United States. https://www.osti.gov/servlets/purl/862895.
@article{osti_862895,
title = {Pu-ZR Alloy high-temperature activation-measurement foil},
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 flux 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 = {8}
}

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