Lumped pseudo fission products during burnup step in MCNP5-ORIGEN coupling system |
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| Affiliation: | 1. Nuclear Research Centre of Birine BP 180 Ain Oussera 17200, Djelfa, Algeria;2. Commissariat of Atomic Energy, 02 bd Frantz Fanon Street, BP 399, 1600, Algiers, Algeria;3. University of Science and Technology Houari Boumediene, Bab Ezzouar, 16111, Algiers, Algeria;1. Research Center Rez Ltd, 250 68 Husinec-Rez 130, Czech Republic;2. University of Defence, Kounicova 65, 662 10 Brno, Czech Republic;3. NRC Kurchatov Institute, 1 Kurchatov Sq., Moscow 123182, Russia;1. Department of Nuclear Engineering, Pakistan Institute of Engineering and Applied Sciences (PIEAS), P. O. Nilore, 45650, Islamabad, Pakistan;2. Department of Physics, COMSTATS Institute of Information Technology, Islamabad, Pakistan;1. Division of Applied Nuclear Physics, Department of Physics and Astronomy, Uppsala University, Uppsala, Sweden;2. Nuclear data Section, International Atomic Energy Commission (IAEA), Vienna, Austria;3. Paul Scherrer Institut, 5232 Villigen, Switzerland;1. Department of Nuclear Engineering, University of California, Berkeley, Berkeley, CA, 94720, USA;2. Department of Physics and Astronomy, Uppsala University, Sweden, Ångström Lab, Lägerhyddsvägen 1, 752 37, Uppsala, Sweden;3. Nuclear Engineering Division, Argonne National Laboratory, Argonne, IL, 60439, USA |
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| Abstract: | Depletion calculation and accurate inventory of fission products in a nuclear system are required for criticality, safety and spent fuel management. Actual trend is to use Monte Carlo methods. It is well known that the fission process produces a large number of nuclides, some of which have a significant impact on the nuclear properties of the core and its behavior. In this study, we propose to determine the influence of fission products on the behavior of the IAEA 10 MW benchmark reactor. Even if nowadays we have powerful computing capability and we can solve the full system of fission products, such calculations are cumbersome and not needed because most of fission products have low absorption rates and therefore their precise concentrations calculation are not required. The practice is to identify and use only the nuclides which can have a significant absorption cross section.From the entire fission products of the available fissionable actinides, 214 nuclides have been considered. Their selection was essentially based on their absorption rates. To carry out the calculation, 81 were treated explicitly and 133 were lumped into pseudo fission products.A computational method has been developed for burnup and criticality calculations using MCNP5-ORIGEN coupling scheme. The MIXE_ACE program was developed and incorporated within this coupling scheme in order to mix and rewrite in ACE format the selected cross sections of the pseudo fission products for each burnup step. The mass weight of the constituent nuclides was used. The initial one group cross sections library for ORIGEN was generated using average flux spectrum in the core.Using the above methodology, an estimation of keff and cross sections during depletion calculations has been carried out for the IAEA 10 MW reactor based on UZrH1.6 fuel. The results are compared to those of ANL (Argonne National Laboratory), MCNP6 and other calculations by using selected fission products from WIMS library. Generally, the results are satisfactory but some discrepancies exist. The differences can be explained mainly by the nature of the fission products considered in the calculation and especially their cross sections. |
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| Keywords: | Fission products End of cycle |
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