Experimental investigation of various pellet geometries to reduce strains in zirconium alloy cladding
Description
In the quest to reduce cladding strain from power ramps and thereby reduce the incidence of defects, various aspects of pellet geometry have been examined. The influence of pellet end squareness was investigated in steady-power irradiation of UO2 with end tapers well in excess of the currently allowable deviation from end squareness, and no increase in postirradiation cladding strains was noticeable. Five ramp tests were performed to examine the effects of pellet length-to-diameter ratio, the width of the load-bearing annulus (shoulder) at the dished end, and the effect of adding a small 450 edge chamfer. Although cladding strains were significantly reduced by changes in pellet geometry, there appears little incentive to do so from the viewpoint of preventing Zircaloy cracking, since defects occurred in rods that had lower overall strains than those that survived
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 45
- Journal Issue
- 2
- Series
- Nucl. Technol.
- Journal Page Range
- 166-176
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11544841
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; CONFIGURATION; FUEL CANS; FUEL PELLETS; STRAINS; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS