Uranium Enrichment Measurements without Calibration Using Gamma Rays Above 100 keV

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The verification of UF{sub 6} shipping cylinders is an important activity in routine safeguards inspections. Current measurement methods using either sodium-iodide or high-purity germanium detectors require calibrations that are not always appropriate for field measurements, because of changes in geometry or container wall thickness. The introduction of the MGAU code demonstrated the usefulness of intrinsically calibrated measurements for inspections. MGAU uses the 100-keV region of the uranium gamma-ray spectrum. The thick walls of UF{sub 6} shipping cylinders and the low-energy analysis preclude the routine use of MGAU for these measurements. We have developed a uranium enrichment measurement method for measurements … continued below

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Ruhter, W. D.; Wang, T. F. & Hayden, C. September 27, 2001.

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The verification of UF{sub 6} shipping cylinders is an important activity in routine safeguards inspections. Current measurement methods using either sodium-iodide or high-purity germanium detectors require calibrations that are not always appropriate for field measurements, because of changes in geometry or container wall thickness. The introduction of the MGAU code demonstrated the usefulness of intrinsically calibrated measurements for inspections. MGAU uses the 100-keV region of the uranium gamma-ray spectrum. The thick walls of UF{sub 6} shipping cylinders and the low-energy analysis preclude the routine use of MGAU for these measurements. We have developed a uranium enrichment measurement method for measurements using high-purity germanium detectors, which do not require calibration, and uranium gamma rays above 100 keV. The method uses seven gamma rays from {sup 235}U and {sup 238}U to determine their relative detection efficiency intrinsically and with an additional gamma ray from {sup 234}U, the relative abundance of these three uranium isotopes. The method uses a function that describes the basic physical processes that predominantly determine the relative detection efficiency curve. These are the detector efficiency, the absorption by the cylinder wall, and the self-absorption by the uranium contents. We will describe this model and initial testing on various uranium materials and detector types.

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PDF-FILE: 8 ; SIZE: 0.2 MBYTES pages

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  • Symposium on International Safeguards: Verification and Nuclear Material Security, Vienna (AT), 10/29/2001--11/01/2001

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  • Report No.: UCRL-JC-142832
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 15005661
  • Archival Resource Key: ark:/67531/metadc1413106

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • September 27, 2001

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  • Jan. 23, 2019, 12:54 p.m.

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  • June 4, 2020, 2:46 p.m.

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Ruhter, W. D.; Wang, T. F. & Hayden, C. Uranium Enrichment Measurements without Calibration Using Gamma Rays Above 100 keV, article, September 27, 2001; California. (https://digital.library.unt.edu/ark:/67531/metadc1413106/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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