Evaluation of the effect of source geometry models on dose rates of waste packages

Georgeta Radulescu, Jabo S. Tang, Thomas W. Doering

Research output: Contribution to journalArticlepeer-review

Abstract

An evaluation of surface dose rates calculated by MCNP with three different source geometric representations for a waste package containing 21 pressurized water reactor (PWR) spent fuel assemblies is provided. The three geometric representations for the source region consist of a radial homogenization inside the waste package cavity, a homogenization of the assembly contents within the transverse dimensions of the assembly, and a detailed geometric model. Conservative dose rates are predicted by the source homogenized inside the cavity, while the detailed and the homogenized assembly models give comparative results.

Original languageEnglish
Pages (from-to)320-323
Number of pages4
JournalJournal of Nuclear Science and Technology
Volume37
DOIs
StatePublished - Mar 2000
Externally publishedYes

Keywords

  • Conservative calculations
  • Detailed geometric representation
  • Gamma and neutron surface dose rate
  • MCNP dose calculations
  • Source homogenization
  • Waste package

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