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Title: IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR

Abstract

A coextruded 2-inch-diameter tubular fuel element of U-2 wt% Zr alloy clad with Zircaloy-2 was irradiated in the Vallecitos Boiling Water Reactor to 1280 Mwd/t burnup with a maximum core temperature of 433 deg C. The purpose of this irradiation was to determine the dimensional stability of the alloy under conditions approaching those contemplated for D/sub 2/O-cooled power reactors. Successive dimensional measurements revealed a sharp change in swelling rate between 700 and 1280 Mwd/t burnup. The amount of swelling increased during this interval from 0.8 to 3.6% (0.7% final cladding strain). This test indicated that the dimensional stability of the U-2 wt% Zr alloy is inferior to that of unalloyed U irradiated under similar conditions. (auth)

Authors:
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) & Co., Wilmington, Del.
OSTI Identifier:
4818425
Report Number(s):
DP-709
NSA Number:
NSA-16-024237
DOE Contract Number:  
AT(07-2)-1
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; BURNUP; DEFORMATION; EXPANSION; EXTRUSION; FUEL CANS; HEAVY WATER COOLANT; IRRADIATION; MATERIALS TESTING; MEASURED VALUES; NEUTRON BEAMS; POWER PLANTS; RADIATION EFFECTS; REACTORS; STABILITY; TEMPERATURE; TUBES; URANIUM ALLOYS; USES; VBWR; VOLUME; ZIRCALOY; ZIRCONIUM ALLOYS

Citation Formats

Quigley, H.C. IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR. United States: N. p., 1962. Web. doi:10.2172/4818425.
Quigley, H.C. IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR. United States. doi:10.2172/4818425.
Quigley, H.C. Sun . "IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR". United States. doi:10.2172/4818425. https://www.osti.gov/servlets/purl/4818425.
@article{osti_4818425,
title = {IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR},
author = {Quigley, H.C.},
abstractNote = {A coextruded 2-inch-diameter tubular fuel element of U-2 wt% Zr alloy clad with Zircaloy-2 was irradiated in the Vallecitos Boiling Water Reactor to 1280 Mwd/t burnup with a maximum core temperature of 433 deg C. The purpose of this irradiation was to determine the dimensional stability of the alloy under conditions approaching those contemplated for D/sub 2/O-cooled power reactors. Successive dimensional measurements revealed a sharp change in swelling rate between 700 and 1280 Mwd/t burnup. The amount of swelling increased during this interval from 0.8 to 3.6% (0.7% final cladding strain). This test indicated that the dimensional stability of the U-2 wt% Zr alloy is inferior to that of unalloyed U irradiated under similar conditions. (auth)},
doi = {10.2172/4818425},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1962},
month = {4}
}