Nuclear medicine program progress report for quarter ending September 30, 1996

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The reactor production yields of tungsten-188 produced by neutron capture by enriched tungsten-186 in the HFIR and other reactors are nearly an order of magnitude lower than expected by calculation using established cross section values. Since neutron capture of tungsten-188 may be the major factor which significantly reduces the observed yields of tungsten-188, the authors have evaluated the possible burn-up cross section of the tungsten-188 product. Tungsten-189 was produced by irradiating a radioactive target containing a known amount of {sup 188}W. In order to reduce the radiation level to an acceptable level (<20% detector dead time), the authors chemically removed ... continued below

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19 p.

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Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Boll, R.; Luo, H.; McPherson, D.W. et al. January 1, 1997.

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Description

The reactor production yields of tungsten-188 produced by neutron capture by enriched tungsten-186 in the HFIR and other reactors are nearly an order of magnitude lower than expected by calculation using established cross section values. Since neutron capture of tungsten-188 may be the major factor which significantly reduces the observed yields of tungsten-188, the authors have evaluated the possible burn-up cross section of the tungsten-188 product. Tungsten-189 was produced by irradiating a radioactive target containing a known amount of {sup 188}W. In order to reduce the radiation level to an acceptable level (<20% detector dead time), the authors chemically removed >90% of {sup 188}Re, which is the decay product of {sup 188}W, prior to irradiation. They were able to confirm the two predominant {gamma}-rays in the decay of {sup 189}W, 260.1 {+-} 1.4 and 421.5 {+-} 1.6 keV. By following the decay of these {gamma}-rays in two sets of experiments, a half-life of 10.8 {+-} 0.3 m was obtained for {sup 189}W. Based on a knowledge of the {sup 188}W content of target (52.6 mBq), neutron flux of 5 {times} 10{sup 13} n {center_dot} s{sup {minus}1} {center_dot} cm{sup {minus}2}, irradiation time of 10 min and with the assumption of 100% intensity for 260.1 and 421.5 keV {gamma}-rays, a cross-section of 12.0 {+-} 2.5 b was calculated for burn-up cross-section of {sup 188}W, which helps explain the greatly reduced production yields of {sup 188}W.

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19 p.

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OSTI as DE98003642

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  • Other Information: PBD: Jan 1997

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  • Other: DE98003642
  • Report No.: ORNL/TM--13336
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/296843 | External Link
  • Office of Scientific & Technical Information Report Number: 296843
  • Archival Resource Key: ark:/67531/metadc687422

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  • January 1, 1997

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  • July 25, 2015, 2:20 a.m.

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  • June 10, 2016, 9:16 p.m.

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Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Boll, R.; Luo, H.; McPherson, D.W. et al. Nuclear medicine program progress report for quarter ending September 30, 1996, report, January 1, 1997; Tennessee. (digital.library.unt.edu/ark:/67531/metadc687422/: accessed December 10, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.