An environment using nuclear inventory codes in combination with the radiation transport code MCNPX for accelerator activation problems

F. X. Gallmeier, W. L. Wilson, M. Wohlmuther, B. Micklich, E. B. Iverson, E. Pitched, W. Lu, H. R. Trellue, Ch Kelsey, G. Muhrer, I. I. Popova, P. D. Ferguson

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

24 Scopus citations

Abstract

We have written and tested a scripting tool which extracts cell-based material, neutron fluxes and spoliation product information from MCNPX output files and drives transmutation calculations using the CINDER '90 code in accelerator-driven systems. This tool was later extended to also drive the alternative transmutation codes ORIHET3 and SP-FISPACT. Another scripting tool was generated for extracting decay gamma spectra and preparing MCNP (X) source decks for remnant decay gamma field calculations. The emphasis of this development effort was put on minimizing the need for user supplied input and simplifying the process of complex activation analyses. Also, an isotope production tally was implemented into MCNPX to enable feeding the transmutation codes without having to post-process the MCNPX history tape with HTAPE3.

Original languageEnglish
Title of host publication8th International Topical Meeting on Nuclear Applications and Utilization of Accelerators, ACCAPP'07
Pages207-211
Number of pages5
StatePublished - 2007
Event8th International Topical Meeting on Nuclear Applications and Utilization of Accelerators, ACCAPP'07 - Pocatello, ID, United States
Duration: Jul 29 2007Aug 2 2007

Publication series

Name8th International Topical Meeting on Nuclear Applications and Utilization of Accelerators, ACCAPP'07

Conference

Conference8th International Topical Meeting on Nuclear Applications and Utilization of Accelerators, ACCAPP'07
Country/TerritoryUnited States
CityPocatello, ID
Period07/29/0708/2/07

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