Uncertainty analysis of the SWEPP PAN assay system for glass waste (content codes 440, 441 and 442)

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INEL is being used as a temporary storage facility for transuranic waste generated by the Nuclear Weapons program at the Rocky Flats Plant. Currently, there is a large effort in progress to prepare to ship this waste to WIPP. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Action Neutron (PAN) radioassay system. This paper discusses a modified statistical sampling and verification approach used to determine the ... continued below

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104 p.

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Blackwood, L.G.; Harker, Y.D.; Meachum, T.R. & Yoon, W.Y. October 1, 1996.

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Description

INEL is being used as a temporary storage facility for transuranic waste generated by the Nuclear Weapons program at the Rocky Flats Plant. Currently, there is a large effort in progress to prepare to ship this waste to WIPP. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Action Neutron (PAN) radioassay system. This paper discusses a modified statistical sampling and verification approach used to determine the total uncertainty of SWEPP PAN measurements for glass waste (content codes 440, 441, and 442) contained in 208 liter drums. In the modified statistical sampling and verification approach, the total performance of the SWEPP PAN nondestructive assay system for specifically selected waste conditions is simulated using computer models. A set of 100 cases covering the known conditions exhibited in glass waste was compiled using a combined statistical sampling and factorial experimental design approach. Parameter values assigned in each simulation were derived from reviews of approximately 100 real-time radiography video tapes of RFP glass waste drums, results from previous SWEPP PAN measurements on glass waste drums, and shipping data from RFP where the glass waste was generated. The data in the 100 selected cases form the multi-parameter input to the simulation model. The reported plutonium masses from the simulation model are compared with corresponding input masses. From these comparisons, the bias and total uncertainty associated with SWEPP PAN measurements on glass waste drums are estimated. The validity of the simulation approach is verified by comparing simulated output against results from calibration measurements using known plutonium sources and two glass waste calibration drums.

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104 p.

Notes

INIS; OSTI as DE97050811

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  • Other Information: PBD: Oct 1996

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  • Other: DE97050811
  • Report No.: INEL--96/0343
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/425278 | External Link
  • Office of Scientific & Technical Information Report Number: 425278
  • Archival Resource Key: ark:/67531/metadc675825

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • October 1, 1996

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • June 14, 2016, 1:11 p.m.

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Blackwood, L.G.; Harker, Y.D.; Meachum, T.R. & Yoon, W.Y. Uncertainty analysis of the SWEPP PAN assay system for glass waste (content codes 440, 441 and 442), report, October 1, 1996; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc675825/: accessed October 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.