Gamma-ray Sptectrometric Characterization of Overpacked CC 104/107 RH-TRU Wastes: Surrogate Tests Metadata

Title

• Main Title Gamma-ray Sptectrometric Characterization of Overpacked CC 104/107 RH-TRU Wastes: Surrogate Tests

Creator

• Author: Hartwell, John Kelvin
  Creator Type: Personal
• Author: Mc Ilwain, Michael Edward
  Creator Type: Personal
• Author: Klann, R. T.
  Creator Type: Personal

Contributor

• Sponsor: United States. Department of Energy.
  Contributor Type: Organization

Publisher

• Name: Idaho National Laboratory
  Place of Publication: [Idaho Falls, Idaho]
  Additional Info: Idaho National Laboratory (INL)

Date

• Creation: 2000-04-01

Language

• English

Description

• Content Description: Development of the gamma-ray spectrometric technique termed GSAK (Gamma-Ray Spectrometry with Acceptable Knowledge) for the characterization of CC104/107 remote-handled transuranic (RH-TRU) wastes continued this year. Proof-of-principle measurements have been completed on the surrogate RH-TRU waste drums configured earlier this year. The GSAK technique uses conventional gamma-ray spectrometry to quantify the detectable fission product content of overpacked RH-TRU drums. These results are then coupled with the inventory report to characterize the waste drum content. The inventory report is based on process knowledge of the waste drum loading and calculations of the isotopic distribution in the spent fuel examined to generate the drummed wastes. Three RH-TRU surrogate drums were configured with encapsulated EBR-II driver fuel rod segments arranged in the surrogate drum assemblies. Segment-specific inventory calculations initially specified the radionuclide content of the fuel segments and thus the surrogate drums. Radiochemical assays performed on representative fuel element segments identified a problem in the accuracy of some of the fission and activation product inventory values and provided a basis for adjustment of the specified surrogate drum inventories. The three waste drum surrogates, contained within their 8.9 cm (3.5 inch) thick steel overpacks, were analyzed by gamma-ray spectrometry at the TREAT facility at Argonne National Laboratory-West. Seven fission and activation product radionuclides (54Mn, 60Co, 125Sb, 134Cs, 137Cs, 144CePr, and 154Eu) were reliably detected. The gamma-ray spectral accuracy was very good. In all cases, a two-sigma error bar constructed about the measured value included the actual drum activity.

Subject

• STI Subject Categories: 12 - Mgmt Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities, 46 - Instrumentation Related To Nuclear Science And Technology
• Keyword: Waste Drums
• Keyword: Spent Fuel
• Keyword: Wastes Activation Product
• Keyword: Fuel Rods
• Keyword: Data
• Keyword: Fission Products
• Keyword: Gamma-Ray Spectrometric Technique
• Keyword: Spectroscopy
• Keyword: Distribution
• Keyword: Radiochemical Assays
• Keyword: Remote-Handled Transuranic (Rh-Tru)
• Keyword: Fuel Elements
• Keyword: Isotopic Distribution
• Keyword: Steels
• Keyword: Inventories
• Keyword: Fission Product
• Keyword: Fission
• Keyword: Spectral Accuracy
• Keyword: Radioisotopes
• Keyword: Spent Fuels
• Keyword: Activation Product
• Keyword: Overpacked
• Keyword: Accuracy

Collection

• Name: Office of Scientific & Technical Information Technical Reports
  Code: OSTI

Institution

• Name: UNT Libraries Government Documents Department
  Code: UNTGD

Resource Type

• Report

Format

• Text

Identifier

• Report No.: INEEL/EXT-00-00567
• Grant Number: DE-AC07-99ID-13727
• DOI: 10.2172/911472
• Office of Scientific & Technical Information Report Number: 911472
• Archival Resource Key: ark:/67531/metadc879458