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:
-
- Westmont, IL
- Publication Date:
- Research Org.:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- OSTI Identifier:
- 862895
- Patent Number(s):
- US 4039378
- Application Number:
- 05/735,566
- Assignee:
- United States of America as represented by United States Energy (Washington, DC)
- 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. 1977.
"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 = {},
url = {https://www.osti.gov/biblio/862895},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Aug 02 00:00:00 EDT 1977},
month = {Tue Aug 02 00:00:00 EDT 1977}
}