Post irradiation examination of self support elements with severe in-reactor cladding corrosion (RM425)
Three self support, natural uranium, I & E production fuel elements, which exhibited serious in-reactor cladding corrosion were selected from several tubes of discharged pieces from PT-IP-272-A-FP. The elements were transferred to the Radiometallurgy Laboratory for detailed examination to determine thickness of the remaining cladding and measure any irradiation induced dimensional changes in the fuel cores. Each element had four support tabs attached to each end and was from Parent Lot KT.009. The fuel geometry of all three was C IV NS.
- Research Organization:
- General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10145639
- Report Number(s):
- HW--70744; ON: DE94010521
- Country of Publication:
- United States
- Language:
- English
Similar Records
Post-irradiation examination of bumper elements with high in-reactor weight losses (RM-418)
Post irradiation examination of elliptical fuel element (RM-416)
Examination of a severely pitted X-8001 alloy clad fuel element (RM-303)
Technical Report
·
Sun Apr 02 23:00:00 EST 1961
·
OSTI ID:10178323
Post irradiation examination of elliptical fuel element (RM-416)
Technical Report
·
Tue Feb 28 23:00:00 EST 1961
·
OSTI ID:10178153
Examination of a severely pitted X-8001 alloy clad fuel element (RM-303)
Technical Report
·
Sun Dec 06 23:00:00 EST 1959
·
OSTI ID:10154956