Behavior of an intentionally defected fuel rod which ruptured during irradiation (Rod BETT 79-64D) (LWBR Development Program)

Technical Report · Tue Jul 01 04:00:00 EDT 1969

DOI:https://doi.org/10.2172/7010761· OSTI ID:7010761

Hersey, B A; Meieran, H B

An intentionally defected Zircaloy-4 clad ceramic pelleted fuel rod (BETT 79-64D) was irradiated in the ETR reactor L-12 loop to a depletion of 8 x 10/sup 20/ fissions/cc. This work was done as part of the LWBR/LSBR fuel element development program. This rod was intentionally defected with a 0.0062-inch diameter defect hole located near the top of the rod. The ZrO/sub 2/ + 29.6 wt % U/sup E/O/sub 2/ fuel material in this rod was in the form of combined-void-volume pellets. The rod failed after 121.2 EFPD of test operation. The purpose of the defect hole was to provide information regarding the effect of defect operation on the performance of a fuel rod with respect to cladding stability, waterlogging potentials, hydrogen pickup in the cladding, and corrosion behavior of an irradiated ceramic fuel material. The post-irradiation examination of this rod and evaluation of its irradiation behavior are described. (NSA 23: 46149)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 7010761
• Report Number(s): WAPD-TM-628
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
BREEDER REACTORS
FAILURES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
PERFORMANCE
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RUPTURES
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS