Published 1978
| Version v1
Journal article
Tube-burst response of irradiated Zircaloy spent-fuel cladding
Description
Transient-heating tube-burst tests were conducted on a 50.8-cm length of Zircaloy cladding obtained from spent-fuel rods irradiated in the H.B. Robinson power reactor to a peak burn-up of 30 MWD/kg. Internal electrical resistance heaters were used to achieve nominal heating rates of 28$degree$C/s for the tests. The tests were conducted in steam and the independent experimental variable was the initial level of helium pressurization. Tube burst pressures varied from 0.965 to 12.514 MPa. No significant difference in burst behavior between unirradiated and spent nuclear fuel Zircaloy cladding was observed experimentally. No influence of axial restraint on burst strains was noted. 9 refs
Additional details
Publishing Information
- Journal Title
- Am. Soc. Test. Mater., Spec. Tech. Publ.
- Journal Issue
- no.681
- Series
- Am. Soc. Test. Mater., Spec. Tech. Publ.
- ISSN
- 0066-0558
Conference
- Title
- 4. symposium on zirconium in the nuclear industry.
- Dates
- 27 - 29 Jun 1978.
- Place
- Stratford-on-Avon, UK.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11558780
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FUEL CANS; LOSS OF COOLANT; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; SPENT FUEL ELEMENTS; STRAINS; STRESSES; TESTING; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ALLOYS; FUEL ELEMENTS; RADIATION EFFECTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-780637--.