Neutron production evaluation from a ADS target utilizing the MCNPX 2.6.0 code

Barros, Graiciany de Paula; Pereira, Cláubia; Veloso, Maria Auxiliadora F.; Costa, Antonella Lombardi; Reis, Paulo Rebelles

doi:10.1590/s0103-97332010000400010

Cited by 11 publications

(7 citation statements)

References 16 publications

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“…The accelerator tube has a radius of 1.5 cm, and the axial position is in the center of the target. The spallation source is represented by a cylindrical neutrons source (in the central cylinder) with a characteristic spectrum of spallation reactions, more details of the spallation source can be found in Reference 25.…”

Section: Methodsmentioning

confidence: 99%

Fuel breeding and waste burnup capabilities of an accelerator‐driven system using thorium and reprocessed fuels

et al. 2020

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Summary Fuel breeding and waste actinide burnup capabilities of a lead‐cooled accelerator‐driven system were evaluated using thorium and reprocessed fuels. The subcritical core simulated was filled with a hexagonal lattice formed by 232ThO2 rods and reprocessed fuel rods. Four types of reprocessed fuel were studied: Group ActiNide EXtraction (GANEX) fuel spiked with 51% of thorium, GANEX fuel spiked with 51% of depleted uranium, Uranium Extraction Plus (UREX+) fuel spiked with 51% of thorium and UREX+ fuel spiked with 51% of depleted uranium. The results indicated that the use of thorium and reprocessed fuels allows thorium regeneration and reduction of the inventory of high radiotoxicity isotopes. The Monte Carlo code SERPENT 2.1.31 was used for the simulations.

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Section: Methodsmentioning

confidence: 99%

Fuel breeding and waste burnup capabilities of an accelerator‐driven system using thorium and reprocessed fuels

et al. 2020

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“…The accelerator tube has a radius of 1.5 cm, and the axial position is in the center of the target. The spallation source is represented by a cylindrical neutrons source (in the central cylinder) with a characteristic spectrum of spallation reactions; more details of the spallation source can be found in Barros . The simulated core was a cylinder of 12 m 3 filled with a hexagonal lattice formed by 156 fuel rods (green).…”

Section: Methodsmentioning

confidence: 99%

Temperature sensitivity analysis for an ADS system using different nuclear data libraries

et al. 2017

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SummaryThe aim is to update the evaluated nuclear data library (ENDL) for nuclides used to simulate accelerator driven systems with JEFF3.1, JEFF3.2, and ENDF/B-VII.1. The applied methodology was, first of all, reproduced to 3 ENDL comparing the cross sections with the ADS Nuclear Data Library at 293.6 K. Second, libraries were processed at working temperature at 1200 K in containing fissile/fissionable material and 900 K for the remaining regions. Third, it is performed a criticality calculation at steady state using all temperatures processed at room temperature and working temperature and compared. Results, indicates the suitable ENDL to perform future burnup calculations. | INTRODUCTIONHybrid systems such as ADS, which coupled a proton beam accelerator and a nuclear core, have been studied for transmutation of minor actinides (MA), energy production, and fuel regeneration. 1-3 One of the most interest options of using an ADS is the capability to produce fissile nuclides such as 233 U from the fertile nuclide 232 Th, maintaining a subcritical core.The nuclear engineering department DEN/UFMG has been studying hybrid systems loaded with reprocessed fuel using nonproliferation means, in which the MA and plutonium are all together in the same fuel matrix. Its main purpose is to transmute the amount of MA by high-energy neutrons produced in spallation reactions or in fission chains. [4][5][6] Nevertheless, to perform a more precisely simulation, it is important to use the appropriate nuclear data library, as well as, the operation temperature. Thus, one of the most important issues in nuclear fission is the proper cross section representation, which may be affected by the temperature causing a Doppler effect.

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“…There was used Bertini intranuclear cascade model for the transport of protons, neutrons, and charged pions. The parameters of this simulation were described in [15].…”

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confidence: 99%

“…Therefore, research interest in spent nuclear fuel transmutation has focused on both accelerator-driven systems and fusiondriven systems. At DEN/UFMG we began about 2006 and some results were obtained [14][15][16]. In this work, the focuses are 233 U production and transuranic transmutation possibility in accelerator-driven systems.…”

Section: Introductionmentioning

confidence: 99%

Study of an ADS Loaded with Thorium and Reprocessed Fuel

Barros¹,

Pereira

Veloso³

et al. 2012

Science and Technology of Nuclear Installations

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Accelerator-driven systems (ADSs) are investigated for long-lived fission product transmutation and fuel regeneration. The aim of this paper is to investigate the nuclear fuel evolution and the neutronic parameters of a lead-cooled accelerator-driven system used for fuel breeding. The fuel used in some fuel rods wasT232hO2forU233production. In the other fuel rods was used a mixture based upon Pu-MA, removed from PWR-spent fuel, reprocessed by GANEX, and finally spiked with thorium or depleted uranium. The use of reprocessed fuel ensured the use ofT232hO2without the initial requirement ofU233enrichment. In this paper was used the Monte Carlo code MCNPX 2.6.0 that presents the depletion/burnup capability, combining an ADS source and kcode-mode (for criticality calculations). The multiplication factor (keff) evolution, the neutron energy spectra in the core at BOL, and the nuclear fuel evolution during the burnup were evaluated. The results indicated that the combined use ofT232hO2and reprocessed fuel allowedU233production without the initial requirement ofU233enrichment.

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Neutron production evaluation from a ADS target utilizing the MCNPX 2.6.0 code

Cited by 11 publications

References 16 publications

Fuel breeding and waste burnup capabilities of an accelerator‐driven system using thorium and reprocessed fuels

Fuel breeding and waste burnup capabilities of an accelerator‐driven system using thorium and reprocessed fuels

Temperature sensitivity analysis for an ADS system using different nuclear data libraries

Study of an ADS Loaded with Thorium and Reprocessed Fuel

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