Data summary report for fission product release Test VI-7

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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 {sup 85}Kr, 52% for {sup 125}Sb, 71% for both {sup 134}Cs and {sup 137}Cs, and 0.04% for {sup 154}Eu. For the non-gamma-emitting species, release values for 42% for I, 4.1% for ... continued below

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53 p.

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Osborne, M.F.; Lorentz, R.A.; Travis, J.R.; Collins, J.L. & Webster, C.S. May 1, 1995.

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Description

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 {sup 85}Kr, 52% for {sup 125}Sb, 71% for both {sup 134}Cs and {sup 137}Cs, and 0.04% for {sup 154}Eu. 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 ZrO{sub 2}, 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.

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53 p.

Notes

INIS; OSTI as TI95013063

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  • Other Information: PBD: May 1995

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  • Other: TI95013063
  • Report No.: NUREG/CR--6318
  • Report No.: ORNL/TM--12937
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/70801 | External Link
  • Office of Scientific & Technical Information Report Number: 70801
  • Archival Resource Key: ark:/67531/metadc702146

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  • May 1, 1995

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • Aug. 2, 2016, 5:47 p.m.

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Osborne, M.F.; Lorentz, R.A.; Travis, J.R.; Collins, J.L. & Webster, C.S. Data summary report for fission product release Test VI-7, report, May 1, 1995; United States. (digital.library.unt.edu/ark:/67531/metadc702146/: accessed July 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.