Current neutronic calculation techniques for modeling the production of IR-192 in HFIR

Josh Peterson-Droogh, Richard Howard

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

4 Scopus citations

Abstract

This paper describes the current methods used to calculate the heating rates of Ir-192 for use in safety basis thermal-hydraulic calculations and to estimate the yield of the activity of the material post-irradiation. Through the use of tools such as MCNP and SCALE/ORIGEN, and with a mesh-based depletion approach, a much more detailed calculation was performed to help optimize the experimental design and to improve understanding of what was happening during the irradiation and decay of the iridium targets. Although the tools and methods outlined in this report were for a specific iridium target, the same procedure could be followed for other targets being irradiated.

Original languageEnglish
Title of host publicationInternational Conference on Physics of Reactors, PHYSOR 2018
Subtitle of host publicationReactor Physics Paving the Way Towards More Efficient Systems
PublisherSociedad Nuclear Mexicana, A.C.
Pages2757-2771
Number of pages15
ISBN (Electronic)9781713808510
StatePublished - 2018
Event2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018 - Cancun, Mexico
Duration: Apr 22 2018Apr 26 2018

Publication series

NameInternational Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems
VolumePart F168384-4

Conference

Conference2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018
Country/TerritoryMexico
CityCancun
Period04/22/1804/26/18

Keywords

  • Ir-192
  • Isotope production
  • MCNP
  • Mesh-based depletion
  • SCALE

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