Data summary report for fission product release test HI-4

Technical Report · Fri Jun 01 04:00:00 EDT 1984

OSTI ID:6795185

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

The fourth in a series of high-temperature fission product release tests was conducted in which a 20.3-cm-long fuel specimen from the Peach Bottom-2 reactor was heated for 20 min at a maximum temperature of approx. 1850/sup 0/C in a flowing steam-helium atmosphere. The test specimen was part of a fuel rod which was irradiated to approx. 10.10 MWd/kg. Posttest metallographic examination of the fuel specimen revealed evidence of cladding melting at each of the transverse cuts that were made. Gas analysis during the test indicated that approx. 54% of the cladding was oxidized. Total oxidation did not occur because of the low stream flow which was used. Gamma spectrometry (GS) and neutron activation (NA) analyses of test components revealed the following releases: (1) GS - 21.1% /sup 85/Kr, 31.7% /sup 137/Cs; and (2) NA - 24.7% /sup 129/I. A value of 35.8% cesium release was determined by counting the fuel rod segment before and after the test. If the pellet-clad gap fission gas inventory had also been available for release in the test, the /sup 85/Kr release would have been 31.3%. Significant releases of radiogenic Rb, Cd, Ag, and Br, as well as trace amounts of Te, La, Ba, Sr, and Eu, were detected by spark-source mass spectrometric analysis. The masses of materials which were transported by carrier gas to the thermal gradient tube (TGT) and filters from the furnace and test specimen were measured by weighing. The concentrations of vapor and aerosol particulates in the gas stream were calculated from these weights.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6795185
• Report Number(s): NUREG/CR-3600; ORNL/TM-9011; ON: DE84012858
• Country of Publication: United States
• Language: English

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