Data summary report for fission product release test HI-5

Technical Report · Wed May 01 04:00:00 EDT 1985

OSTI ID:5435091

Osborne, M F; Collins, J L; Lorenz, R A; Norwood, K S; Travis, J R; Webster, C S

The fifth in a series of high-temperature fission product release tests was conducted for 20 min at 1700/sup 0/C in flowing steam. The test specimen was a 15.2-cm-long section of a fuel rod from the Oconee 1 PWR which had been irradiated to a burnup of approx.38.3 MWd/kg. Using an induction furnace, it was heated under simulated LWR accident conditions in a hot cell. Posttest inspection showed severe oxidation and fragmentation of a portion of the fuel specimen, but no cladding melting was apparent. Based on fission product inventories calculated by ORIGEN, analyses of test components showed total releases from the fuel of 19.9% for /sup 85/Kr, 22.4% for /sup 129/I, 18.0% for /sup 110m/Ag, and 20.3% for /sup 137/Cs. A smaller fraction of the /sup 125/Sb (0.326%) was released from the fuel, and approx.99% of the /sup 110m/Ag and /sup 125/Sb was retained in the furnace. Posttest analysis of the fuel specimen indicated a /sup 134/Cs release of 24.5%, which is reasonably good agreement. This test was conducted at the same temperature as test HI-2 but with the steam flow reduced in order to determine the effect of cladding and fuel oxidation on fission product release. The release of Cs, I, and Kr was less than half that in HI-2, but it is not certain that the degree of oxidation alone was responsible for the difference. The large axial crack that occurred in HI-2 probably was a significant factor.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5435091
• Report Number(s): NUREG/CR-4037; ORNL/TM-9437; ON: TI85012208
• Country of Publication: United States
• Language: English

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