Calculational methods used in evaluating the multi-isotope production assembly experiment

Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6127232

Carter, L L; Wootan, D W

The multi-isotope production (MIP) assembly was irradiated in the Fast Flux Test Facility (FFTF) to help reduce uncertainties in the nuclear data in preparation for a possible future mission as a facility for producing {sup 238}Pu and to demonstrate the capability of FFTF to produce many other beneficial radioisotopes. A detailed Monte Carlo neutron photon (MCNP) model of this assembly was created to provide a calculational basis for comparison with experimental results. This calculation was unique because of the heterogeneous configuration of the model and the diverse neutron and photon environments. A number of tools were developed to facilitate creating the model and assure accuracy in modeling the assembly. The lessons learned from the modeling of the MIP assembly calculations may be applicable to other complicated MCNP geometries. The primary purpose of the MIP test was to verify the calculation of the {sup 238}Pu production rate and the {sup 236}Pu contamination of the {sup 238}Pu material, which must be kept within acceptable limits.

• OSTI ID: 6127232
• Report Number(s): CONF-900608-; CODEN: TANSA; TRN: 91-008321
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

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