IRRADIATION BEHAVIOR OF RESTRAINED AND VENTED URANIUM-2 w/o ZIRCONIUM ALLOY. Final Report-Programs 6.1.22 and 6.1.27
Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded by a natural uranium--2 wt% zirconium alloy sleeve. Eight of the specimens were irradiated to burnups of the enriched core of 6.9 to 12.8% of all atoms (1.2 to 2.2 at.% of the duplex assembly) at maximum fuel temperatures ranging from 280 to 760 deg C. Most of the clad specimens exhibited negligible volume increases as a result of irradiation. Two specimens containing central vents but unclad were irradiated together with the clad specimens in an attempt to differentiate between the effects due to a central vent and the effects due to cladding. The central vent in itself did not appear to reduce the swelling characteristics of the alloy. Mechanical restraint appeared to have extended the useful operating temperatures of the metallic fuel alloy by at least 200 deg C and also greatly extended the burnup levels to which the fuel could be irradiated. (auth)
- Research Organization:
- Argonne National Lab., Ill.
- DOE Contract Number:
- W-31-109-ENG-38
- NSA Number:
- NSA-16-032136
- OSTI ID:
- 4785339
- Report Number(s):
- ANL-6431
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
Similar Records
PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY, 1959
PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JANUARY 1959