Cross sections for fuel depletion and radioisotope production calculations in TRIGA reactors
- National Institute of Nuclear Research (United States)
For TRIGA Reactors, the fuel depletion and isotopic inventory calculations, depends on the computer code and in the cross sections of some important actinides used. Among these we have U-235, U-238, Pu-239, Pu-240 and Pu-241. We choose ORIGEN2, a code with a good reputation in this kind of calculations, we observed the cross sections for these actinides in the libraries that we have (PWR's and BWR), the fission cross section for U-235 was about 50 barns. We used a PWR library and our results were not satisfactory, specially for standard elements. We decided to calculate cross sections more suitable for our reactor, for that purpose we simulate the standard and FLIP TRIGA cells with the transport code WIMS. We used the fuel average flux and COLAPS (a home made program), to generate suitable cross sections for ORIGEN2, by collapsing the WIMS library cross sections of these nuclides. For the radioisotope production studies using the Central Thimble, we simulate the A and B rings and used the A average flux to collapse cross sections. For these studies, the required nuclides sometimes are not present in WIMS library, for them we are planning to process the ENDF/B data, with NJOY system, and include the cross sections to WIMS library or to collapse them using the appropriate average-flux and the program COLAPS. (author)
- Research Organization:
- General Atomics, San Diego, CA (United States)
- OSTI ID:
- 21141167
- Report Number(s):
- INIS-US-09N0001; TRN: US09N0013020804
- Resource Relation:
- Conference: 14. U.S. TRIGA users conference, San Diego, CA (United States), 5-8 Apr 1994; Other Information: Country of input: International Atomic Energy Agency (IAEA); Related Information: In: 14. U.S. TRIGA users conference. Final program and summary of papers, 50 pages.
- Country of Publication:
- United States
- Language:
- English
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