Gamma spectrometry and calibration methods used in neutron dosimetry

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Neutron activation rates are calculated from measured gamma-ray spectral data obtained from calibrated lithium drifted germanium (Ge(Li)) detectors. The calibration techniques, which include energy, efficiency, pulse height analyzer data reduction, and geometry factors, are discussed. Problems encountered when analyzing highly radioactive samples, specifically random coincidence summing, sample size, air absorption, and use of absorbers, are also discussed briefly. To illustrate the accuracy achievable, the reduction of gamma-ray spectral data and the calculation of reaction rates by three independent laboratories are presented for both fission and nonfission foils to a precision of +-1 to 2% (1sigma). The application of these neutron ... continued below

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Pages: 11

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Malewicki, R.L.; Heinrich, R.R. & Popek, R.J. January 1, 1979.

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Description

Neutron activation rates are calculated from measured gamma-ray spectral data obtained from calibrated lithium drifted germanium (Ge(Li)) detectors. The calibration techniques, which include energy, efficiency, pulse height analyzer data reduction, and geometry factors, are discussed. Problems encountered when analyzing highly radioactive samples, specifically random coincidence summing, sample size, air absorption, and use of absorbers, are also discussed briefly. To illustrate the accuracy achievable, the reduction of gamma-ray spectral data and the calculation of reaction rates by three independent laboratories are presented for both fission and nonfission foils to a precision of +-1 to 2% (1sigma). The application of these neutron activation rates to neutron dosimetry is discussed. An unfolded neutron spectrum is illustrated, along with energy sensitivity limits for many reactions of dosimetry interest.

Physical Description

Pages: 11

Notes

Dep. NTIS, PC A02/MF A01.

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  • 23. conference on analytical chemistry in energy technology, Gatlinburg, TN, USA, 9 Oct 1979

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  • Report No.: CONF-791049-23
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 5547229
  • Archival Resource Key: ark:/67531/metadc1093693

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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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  • January 1, 1979

Added to The UNT Digital Library

  • Feb. 10, 2018, 10:06 p.m.

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  • April 19, 2018, 10:22 a.m.

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Malewicki, R.L.; Heinrich, R.R. & Popek, R.J. Gamma spectrometry and calibration methods used in neutron dosimetry, article, January 1, 1979; Illinois. (digital.library.unt.edu/ark:/67531/metadc1093693/: accessed November 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.