IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR
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)
- Research Organization:
- Du Pont de Nemours (E.I.) & Co., Wilmington, Del.
- NSA Number:
- NSA-16-024237
- OSTI ID:
- 4818425
- Report Number(s):
- DP-709
- Country of Publication:
- United States
- Language:
- English
Similar Records
POWER REACTOR PROGRAM. Progress Report to E.I. du Pont de Nemours and Company for the Period April 1, 1959 through April 30, 1959
Hanford contribution for the 16th high temperature fuels committee meeting, May, 1963
Swelling behavior of N-Reactor fuel elements
Technical Report
·
Fri Aug 14 00:00:00 EDT 1959
·
OSTI ID:4246864
Hanford contribution for the 16th high temperature fuels committee meeting, May, 1963
Technical Report
·
Tue Apr 16 23:00:00 EST 1963
·
OSTI ID:10147722
Swelling behavior of N-Reactor fuel elements
Technical Report
·
Mon Jun 15 00:00:00 EDT 1964
·
OSTI ID:7038736