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

Abstract

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 PANmore » 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.« less

Authors:
; ; ;
Publication Date:
Research Org.:
Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
OSTI Identifier:
425278
Report Number(s):
INEL-96/0343
ON: DE97050811; TRN: 97:003099
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Oct 1996
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 40 CHEMISTRY; WASTE FORMS; RADIOISOTOPE SCANNING; ALPHA-BEARING WASTES; NEUTRON DETECTORS; ACCURACY; NONDESTRUCTIVE ANALYSIS; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA

Citation Formats

Blackwood, L G, Harker, Y D, Meachum, T R, and Yoon, W Y. Uncertainty analysis of the SWEPP PAN assay system for glass waste (content codes 440, 441 and 442). United States: N. p., 1996. Web. doi:10.2172/425278.
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). United States. doi:10.2172/425278.
Blackwood, L G, Harker, Y D, Meachum, T R, and Yoon, W Y. Tue . "Uncertainty analysis of the SWEPP PAN assay system for glass waste (content codes 440, 441 and 442)". United States. doi:10.2172/425278. https://www.osti.gov/servlets/purl/425278.
@article{osti_425278,
title = {Uncertainty analysis of the SWEPP PAN assay system for glass waste (content codes 440, 441 and 442)},
author = {Blackwood, L G and Harker, Y D and Meachum, T R and Yoon, W Y},
abstractNote = {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.},
doi = {10.2172/425278},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1996},
month = {10}
}