skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Uncertainty analysis of the SWEPP drum assay system for graphite content code 300

Abstract

The Idaho National Engineering Laboratory is being used as a temporary storage facility for transuranic waste generated by the U.S. Nuclear Weapons program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to prepare to ship this waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. 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 Active Neutron (PAN) radioassay system. This paper discusses a modified statistical sampling and verification approach used to determine the total uncertainty of a SWEPP/PAN measurement. In this modified approach the total performance of the SWEPP/PAN nondestructive assay system is simulated using computer models of the assay system and the resultant output is compared with the known input to assess the total uncertainty. The first waste form to be tested using this approach is weapons grade plutonium-contaminated graphite molds contained in 207 liter drums. The validity of the simulation approach is verified by comparing simulated output against results from calibration measurements usingmore » known plutonium sources and a graphite waste form calibration drum. For actual graphite waste form conditions, a set of 50 cases covering a statistical sampling of the conditions exhibited in graphite wastes was compiled using a Latin hypercube statistical sampling approach. The distributions from which Latin hypercube sample was drawn was derived from reviews of approximately 100 real-time radiography video tapes of RFP graphite waste drums, results from previous SWEPP/PAN measurements on graphite waste drums, and shipping data from RFP where the graphite waste was generated.« less

Authors:
; ;
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
130646
Report Number(s):
INEL-95/0475
ON: DE96002355; TRN: 96:000109
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Sep 1995
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; IDAHO NATIONAL ENGINEERING LABORATORY; RADIOACTIVE WASTE MANAGEMENT; ALPHA-BEARING WASTES; LAND TRANSPORT; PACKAGING; RADIOASSAY; WIPP; RADIOACTIVE WASTE STORAGE; CONTAINERS; GRAPHITE

Citation Formats

Harker, Y D, Blackwood, L G, and Meachum, T R. Uncertainty analysis of the SWEPP drum assay system for graphite content code 300. United States: N. p., 1995. Web.
Harker, Y D, Blackwood, L G, & Meachum, T R. Uncertainty analysis of the SWEPP drum assay system for graphite content code 300. United States.
Harker, Y D, Blackwood, L G, and Meachum, T R. Fri . "Uncertainty analysis of the SWEPP drum assay system for graphite content code 300". United States.
@article{osti_130646,
title = {Uncertainty analysis of the SWEPP drum assay system for graphite content code 300},
author = {Harker, Y D and Blackwood, L G and Meachum, T R},
abstractNote = {The Idaho National Engineering Laboratory is being used as a temporary storage facility for transuranic waste generated by the U.S. Nuclear Weapons program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to prepare to ship this waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. 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 Active Neutron (PAN) radioassay system. This paper discusses a modified statistical sampling and verification approach used to determine the total uncertainty of a SWEPP/PAN measurement. In this modified approach the total performance of the SWEPP/PAN nondestructive assay system is simulated using computer models of the assay system and the resultant output is compared with the known input to assess the total uncertainty. The first waste form to be tested using this approach is weapons grade plutonium-contaminated graphite molds contained in 207 liter drums. The validity of the simulation approach is verified by comparing simulated output against results from calibration measurements using known plutonium sources and a graphite waste form calibration drum. For actual graphite waste form conditions, a set of 50 cases covering a statistical sampling of the conditions exhibited in graphite wastes was compiled using a Latin hypercube statistical sampling approach. The distributions from which Latin hypercube sample was drawn was derived from reviews of approximately 100 real-time radiography video tapes of RFP graphite waste drums, results from previous SWEPP/PAN measurements on graphite waste drums, and shipping data from RFP where the graphite waste was generated.},
doi = {},
url = {https://www.osti.gov/biblio/130646}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {9}
}

Technical Report:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that may hold this item. Keep in mind that many technical reports are not cataloged in WorldCat.

Save / Share: