An environment using nuclear inventory codes in combination with radiation transport code MCNPX for accelerator activation problems
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
We have written and tested a scripting tool which extracts cell-based material, neutron fluxes and spallation 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.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Spallation Neutron Source (SNS)
- Sponsoring Organization:
- USDOE Office of Science (SC)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1027387
- Resource Relation:
- Conference: 8. International Topical Meeting on Nuclear Applications and Utilization of Accelerators - AccApp07, Pocatello, ID (United States), 30 Jul - 2 Aug 2007
- Country of Publication:
- United States
- Language:
- English
Similar Records
The CINDER'90 transmutation code package for use in accelerator applications in combination with MCNPX
MCNPX-CINDER'90 Simulation of Photonuclear Mo-99 Production Experiments