Data summary report for fission product release test VI-7
Title | Data summary report for fission product release test VI-7 PDF eBook |
Author | M. F. Osborne |
Publisher | |
Pages | 0 |
Release | 1995 |
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Data Summary Report for Fission Product Release Test VI-3
Title | Data Summary Report for Fission Product Release Test VI-3 PDF eBook |
Author | |
Publisher | |
Pages | 60 |
Release | 1990 |
Genre | Fission products |
ISBN | 9780160235627 |
Data Summary Report for Fission Product Release Test VI-4
Title | Data Summary Report for Fission Product Release Test VI-4 PDF eBook |
Author | |
Publisher | |
Pages | 60 |
Release | 1991 |
Genre | Fission products |
ISBN |
Data Summary Report for Fission Product Release Test VI-1
Title | Data Summary Report for Fission Product Release Test VI-1 PDF eBook |
Author | |
Publisher | |
Pages | 59 |
Release | 1989 |
Genre | Fission products |
ISBN |
Data Summary Report for Fission Product Release Test VI-7, NUREG/CR-6318, U.S.N.R.C., May 1995
Title | Data Summary Report for Fission Product Release Test VI-7, NUREG/CR-6318, U.S.N.R.C., May 1995 PDF eBook |
Author | |
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Data Summary Report for Fission Product Release Test VI-2
Title | Data Summary Report for Fission Product Release Test VI-2 PDF eBook |
Author | |
Publisher | |
Pages | 59 |
Release | 1989 |
Genre | Fission products |
ISBN |
Data Summary Report for Fission Product Release Test VI-7
Title | Data Summary Report for Fission Product Release Test VI-7 PDF eBook |
Author | |
Publisher | |
Pages | 53 |
Release | 1995 |
Genre | |
ISBN |
Test VI-7 was the final test in the VI series conducted in the vertical furnace. The fuel specimen was a 15.2-cm-long section of a fuel rod from the Monticello boiling water reactor (BWR). The fuel had experienced a burnup of (approximately)-40 Mwd/kg U. It was heated in an induction furnace for successive 20-min periods at 2000 and 2300 K in a moist air-helium atmosphere. Integral releases were 69% for 85Kr, 52% for 125Sb, 71% for both 134Cs and 137Cs, and 0.04% for 154Eu. For the non-gamma-emitting species, release values for 42% for I, 4.1% for Ba, 5.3% for Mo, and 1.2% for Sr were determined. The total mass released from the furnace to the collection system, including fission products, fuel, and structural materials, was 0.89 g, with 37% being collected on the thermal gradient tubes and 63% downstream on filters. Posttest examination of the fuel specimen indicated that most of the cladding was completely oxidized to ZrO2, but that oxidation was not quite complete at the upper end. The release behaviors for the most volatile elements, Kr and Cs, were in good agreement with the ORNL-Booth Model.