Validation of a Monte Carlo based depletion methodology via High Flux Isotope Reactor HEU post-irradiation examination measurements

The purpose of this study is to validate a Monte Carlo based depletion methodology by comparing calculated post-irradiation uranium isotopic compositions in the fuel elements of the High Flux Isotope Reactor (HFIR) core to values measured using uranium mass-spectrographic analysis Three fuel plates were analyzed two from the outer fuel element (OH) and one from the inner fuel element (IFE). Fuel plates O-111-8, O-350-1, and I-417-24 from outer fuel elements 5-O and 21-O and inner fuel element 49-I, respectively, were selected for examination. Fuel elements 5-O, 21-O, and 49-I were loaded into HFIR during cycles 4, 16, and 35, respectively (mid to late 1960s). Approximately one year after each of these elements were irradiated, they were transferred to the High Radiation Level Examination Laboratory (HRLEL) where samples from these fuel plates were sectioned and examined via uranium mass-spectrographic analysis The isotopic composition of each of the samples was used to determine the atomic percent of the uranium isotopes A Monte Carlo based depletion computer program. ALEPH, which couples the MCNP and ORIGEN codes, was utilized to calculate the nuclide inventory at the end-of-cycle (EOC) A current ALEPH/MCNP input for HFIR fuel cycle 400 was modified to replicate cycles 4,16, and 35 The control element withdrawal curves and flux trap loadings were revised, as well as the radial zone boundaries and nuclide concentrations in the MCNP model The calculated EOC uranium isotopic compositions for the analyzed plates were found to be in good agreement with measurements, which reveals that ALEPH/MCNP can accurately calculate burn-up dependent uranium isotopic concentrations for the HFIR core. The spatial power distribution in HFIR changes significantly as irradiation time increases due to control element movement Accurate calculation of the end-of-life uranium isotopic inventory is a good indicator that the powerdistnbution variation as a function of space and time is accurately calculated, i e an integral check Hence, the time dependent heat generation source terms needed for reactor core thermal hydraulic analysis, if dei wed from this methodology, have been shown to be accurate for highly enriched uranium (HEU) fuel (C) 2010 Elsevier B V. All rights reserved.