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Automated three dimensional depletion capability for the Pennsylvania State University research reactor

  • C. Tippayakul
  • , K. N. Ivanov
  • , C. F. Sears
  • , G. M. Morlang
  • , B. J. Heidrich

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

4 Scopus citations

Abstract

This paper describes the new depletion calculation capability for the Pennsylvania State University research reactor (PSBR). The calculation scheme employs the general purpose Monte Carlo code MCNP4C coupled with the versatile nuclear depletion code ORIGEN2.2 via the recently developed interface code, TRIGSIM. The main functions of the TRIGSIM code are automatic generation of MCNP and ORIGEN inputs from one TRIGSIM input and interfacing the data exchange between the two codes. The PSBR core loading 1, core loading 2 and core loading 3 were modeled using TRIGSIM code. The excess reactivity results from the core calculations have shown reasonable agreement compared to the measured excess reactivity from the operational log book.

Original languageEnglish
Title of host publicationProceedings of the PHYSOR 2004
Subtitle of host publicationThe Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Pages737-746
Number of pages10
StatePublished - 2004
EventPHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments - Chicago, IL, United States
Duration: Apr 25 2004Apr 29 2004

Publication series

NameProceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Conference

ConferencePHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Country/TerritoryUnited States
CityChicago, IL
Period04/25/0404/29/04

Keywords

  • Depletion calculation
  • Fuel management
  • MCNP
  • Monte Carlo calculation
  • ORIGEN
  • Research reactor

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