Data summary report for fission product release test VI-2

Technical Report · Fri Sep 01 04:00:00 EDT 1989

DOI:https://doi.org/10.2172/5678736· OSTI ID:5678736

Osborne, M. F.; Collins, J. L.; Lorenz, R. A.; Travis, J. R.; Webster, C. S. ^[1]

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1. Oak Ridge National Lab., TN (USA)

The second in a series of high-temperature fission product release tests in a new vertical test apparatus was conducted. The 15.2-cm-long test specimen had been irradiated to a burnup of {approximately}42 MWd/kg. Using an induction furnace and collection apparatus mounted in a hot cell, it was heated under simulated LWR accident conditions for 60 min at 2300 K in flowing steam. Posttest inspection showed severe oxidation of the cladding but only minimal fragmentation of the Zircaloy cladding. Based on fission product inventories in the fuel, total releases of 30.7% for {sup 85}Kr, 8.93% for {sup 110m}Ag, 68.2% for {sup 125}Sb, and 63.4% for {sup 137}Cs were measured. Smaller release fractions for many other fission products and fuel material -- uranium and plutonium -- were determined also. Total mass release from the furnace to the collection system was 1.08 g. Comparison of the results from this test showed reasonable agreement with the results from two earlier tests at similar conditions. The release rate coefficients from the six tests in the HI series and tests VI-1 and VI-2 fall significantly below a widely accepted standard used in LWR safety analyses. 22 refs., 24 figs., 16 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5678736
• Report Number(s): NUREG/CR-5340; ORNL/TM--11105; ON: TI90001032
• Country of Publication: United States
• Language: English

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