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ASNC upgrade for nuclear material accountancy of ACPF

  • Hee Seo*
  • , Seong Kyu Ahn
  • , Chaehun Lee
  • , Jong Myeong Oh
  • , Seonkwang Yoon
  • *Corresponding author for this work
  • Korea Atomic Energy Research Institute
  • University of Science and Technology UST

Research output: Contribution to journalJournal articlepeer-review

Abstract

A safeguards neutron coincidence counter for nuclear material accountancy of the Advanced spent-fuel Conditioning Process Facility (ACPF), known as the ACP Safeguards Neutron Counter (ASNC), was upgraded to improve its remote-handling and maintenance capabilities. Based on the results of the previous design study, the neutron counter was completely rebuilt, and various detector parameters for neutron coincidence counting (i.e., high-voltage plateau, efficiency profile, dead time, die-away time, gate length, doubles gate fraction, and stability) were experimentally determined. The measurement data showed good agreement with the MCNP simulation results. To the best of the authors’ knowledge, the ASNC is the only safeguards neutron coincidence counter in the world that is installed and operated in a hot-cell. The final goals to be achieved were (1) to evaluate the uncertainty level of the ASNC in nuclear material accountancy of the process materials of the oxide-reduction process for spent fuels and (2) to evaluate the applicability of the neutron coincidence counting technique within a strong radiation field (e.g., in a hot-cell environment).

Keywords

  • Neutron detector
  • Non-destructive assay
  • Nuclear material accountancy
  • Safeguards

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