Burnup of Cadmium Decoupler Material in the Spallation Neutron Source Moderators

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At the Spallation Neutron Source being constructed at Oak Ridge National Laboratory, power levels will be greater than at any other operating pulsed spallation neutron scattering facility. Some of the moderators at the facility will contain cadmium that will be used to tailor neutron time distributions by absorbing low-energy neutrons. Because of the higher operating power levels, indications are that there will be considerable burnup of this cadmium during the lifetime of the moderators. Cadmium burnup rates have been calculated for locations around the moderators. Assumed operating conditions for these calculations were a 2-mA beam of 1-GeV protons on the ... continued below

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Murphy, BD August 21, 2001.

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At the Spallation Neutron Source being constructed at Oak Ridge National Laboratory, power levels will be greater than at any other operating pulsed spallation neutron scattering facility. Some of the moderators at the facility will contain cadmium that will be used to tailor neutron time distributions by absorbing low-energy neutrons. Because of the higher operating power levels, indications are that there will be considerable burnup of this cadmium during the lifetime of the moderators. Cadmium burnup rates have been calculated for locations around the moderators. Assumed operating conditions for these calculations were a 2-mA beam of 1-GeV protons on the mercury target for 5,000 operating hours per year and a three-year lifetime for the moderators and inner-plug assembly. With the present proposed cadmium thickness in the moderator region (0.05 cm), Monte Carlo calculations indicate considerable depletion of the active cadmium isotope. In places, the calculations indicate complete depletion. An obvious solution to the problem would be to increase the cadmium thickness with a concomitant increase in heat load. Results from some cadmium heating calculations are also presented for a cadmium thickness of 0.05 cm.

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  • ANS Accelerator Applications 2001 Conference, Reno, NV (US), 11/11/2001--11/15/2001

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  • Report No.: P01-111661
  • Grant Number: AC05-00OR22725
  • Office of Scientific & Technical Information Report Number: 788645
  • Archival Resource Key: ark:/67531/metadc721015

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  • August 21, 2001

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  • Sept. 29, 2015, 5:31 a.m.

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  • March 30, 2016, 4:59 p.m.

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Murphy, BD. Burnup of Cadmium Decoupler Material in the Spallation Neutron Source Moderators, article, August 21, 2001; Tennessee. (digital.library.unt.edu/ark:/67531/metadc721015/: accessed August 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.