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A neutron monitor for in-situ real-time determination of transuranics in a processed waste effluent stream

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Abstract

A pilot plant operation at the Savannah River Site will remove 90Sr, 137Cs, and transuranics from a high-level liquid waste stream prior to encapsulation in a Saltstone Facility. Monitors are required to determine the concentrations of all radionuclides, including transuranics, in real-time on this processed waste stream. A neutron counter used to measure the concentration of each actinide isotope present in the stream is described. The neutron counter assembly consists of nested annular layers of shielding, reflectors, detectors, and moderators. On-line, live-time system control and calibration is provided by a time-tagged neutron source embedded in the moderator assembly.

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References

  1. H. Matsunobu, T. Oku, S. Iijima, Y. Naito, F. Masukawa, R. Nakasima, JAERI-1324, 1992.

  2. MCNP4a: Monte Carlo N-Particle Transport Code System, CCC-200, distributed by Radiation Shielding Information Center at Oak Ridge National Laboratory.

  3. MCNP4A—A General Monte Carlo N-Particle Transport Code: Version 4A; J. F. Briesmeister (Ed.), LA-12625-M, November 1993.

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Authors and Affiliations

  1. Pacific Northwest National Laboratory, P.O. Box 999, Richland, WA, 99352, USA

    R. L. Brodzinski, R. A. Craig, W. K. Hensley, E. A. Lepel & J. E. Smart

  2. NucSafe LLC, 241 Tracy Allison Drive, c[Clinton, TN, 37716, USA

    R. Seymour

Authors
  1. R. L. Brodzinski
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  2. R. A. Craig
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  3. W. K. Hensley
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  4. E. A. Lepel
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  5. R. Seymour
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  6. J. E. Smart
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Brodzinski, R.L., Craig, R.A., Hensley, W.K. et al. A neutron monitor for in-situ real-time determination of transuranics in a processed waste effluent stream. Journal of Radioanalytical and Nuclear Chemistry 248, 279–281 (2001). https://doi.org/10.1023/A:1010643017376

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  • DOI: https://doi.org/10.1023/A:1010643017376

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