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Claubia Pereira - One of the best experts on this subject based on the ideXlab platform.

  • Neutronic evaluation of CANDU-6 core using Reprocessed Fuels
    Brazilian Journal of Radiation Sciences, 2020
    Co-Authors: Clarysson Alberto Mello Da Silva, Carlos Eduardo Velasquez Cabrera, Michel Cleberson Bernardo De Almeida, Rochkhudon Batista De Faria, Claubia Pereira
    Abstract:

    The spent Fuel from a PWR still contains some amount of fissile materials depending on their initial enrichment and the burnup. Thus, spent Fuel from PWRs containing about 1.5% of fissile material could be used as Fuel for CANDU reactors after some fission products are removed from it. Thus, an important proposal is the DUPIC cycle, where spent Fuels from a PWR are packaged into a CANDU Fuel bundle using mechanical reprocessing but without the need of chemical reprocessing. When it is reFueled with Reprocessed Fuel, the reactivity of the system increases, and this behavior may affect the safety parameters of the reactor. Therefore, this work studies the neutronic parameters of two reprocessing Fuel techniques: AIROX and OREOX, which are evaluated for two different cores configuration. The first one considers heavy water as a moderator and coolant. The second one considers heavy water and light water as moderator and coolant respectively. These studies evaluate the core behavior based on the different number of Reprocessed Fuels channels and compare them with the reference core. To perform the simulation the MCNPX was used to calculate the effective multiplication factor, Fuel temperature coefficient of reactivity, void reactivity coefficient, and neutron flux, which were evaluated at steady state condition for the different cases. The results show that the presence of parasitic absorbers in the Reprocessed Fuels hardens the neutron spectrum. This behavior provokes an increase in the core reactivity, in the Fuel temperature coefficient and in the void reactivity coefficient. Among these parameters, the use of light water reduces the core reactivity but do not improve the Fuel temperature coefficient and the void reactivity coefficient.

  • Criticality and depletion analysis of Reprocessed Fuel spiked with thorium in a PWR core
    Nuclear Engineering and Design, 2020
    Co-Authors: Victor Faria De Castro, Carlos E. Velasquez, Claubia Pereira
    Abstract:

    Abstract The aim of this work is to preliminarily evaluate the behaviour of a PWR core based on Brazilian Angra 2 when Reprocessed Fuel spiked with thorium (TRU) is inserted. The TRU Fuel insertion was evaluated and compared with the standard UO2 to assess the possibility of its use in already established PWRs. For the core calculations, the neutronic parameters analysed were the infinite multiplication factor, the Fuel evolution during the burnup, reactivity coefficients and the conversion ratio (CR). The core results indicated that the insertion of burnable poison rods is not necessary if Reprocessed Fuel spiked with thorium is used, because the TRU Fuel behave like a neutron absorber. Besides, the conversion ratio obtained was more significant than the standard UO2 Fuel, indicating the possibility of extending the burnup. The Fuel assemblies without absorbers were then modelled and analysed, considering the kinf evolution and the delayed neutron fraction (DNF) during burnup. The assembly results show that the DNF of the assemblies using Reprocessed Fuel is smaller than the standard assemblies for all of them, which is due to the 239Pu presence and the 233U production that contribute to the low values obtained for delayed fission neutron fraction. These lower values of DNF suggest that an assembly Fuelled with TRU Fuel needs to be improved in order to raise the safety of the system. In general, the insertion of the TRU Fuel in a PWR system presents improvements in terms of Fuel economy and waste reduction, although it brings several neutronic alterations that need to be assessed in depth in order to ensure the safety of the reactor. The core model was based on the Final Safety Analysis Report (FSAR) of the Angra-2 reactor and simulated with SCALE6.0 nuclear code package.

  • Criticality safety analysis of spent Fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 Fuels
    Brazilian Journal of Radiation Sciences, 2019
    Co-Authors: Claubia Pereira, Victor Faria De Castro, Jéssica P. Achilles, Fabiano Pereira Cardoso, Maria Auxiliadora F. Veloso
    Abstract:

    A spent Fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses Reprocessed Fuels. PWR nuclear Fuel assemblies with four types of Fuels were considered: standard PWR Fuel, MOX Fuel, thorium-uranium Fuel and Reprocessed transuranic Fuel spiked with thorium. The MOX and UO 2 benchmark model was evaluated using SCALE 6.0 code with KENO-V transport code and then, adopted as a reference for other Fuels compositions. The four Fuel assemblies were submitted to irradiation at normal operation conditions. The burnup calculations were obtained using the TRITON sequence in the SCALE 6.0 code package. The Fuel assemblies modeled use a benchmark 17x17 PWR Fuel assembly dimensions. After irradiation, the Fuels were inserted in the pool. The criticality safety limits were performed using the KENO-V transport code in the CSAS5 sequence. It was shown that mixing a quarter of Reprocessed Fuel withUO 2 Fuel in the pool, it would not need to be resized

  • Thorium and Transuranic (TRU) Advanced Fuel Cycle: An Option for Brazilian Nuclear Plants
    Thorium Energy for the World, 2016
    Co-Authors: Fabiana. B. A. Monteiro, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, Rochkhudson. B. Faria, Ângela Fortini, Diego M. De Almeida, A.l. Costa
    Abstract:

    A typical pressurised water reactor (PWR) Fuel element containing TRU–Th Fuel cycle was simulated. The study analysed the behaviour of thorium insertion spiked with Reprocessed Fuel by considering different enrichments that varied from 5.5 to 7.0 %. The Reprocessed Fuels were obtained by using the ORIGEN 2.1 code from a burnt PWR standard Fuel (33,000 MWd/tHM burned), with 3.1 % of initial enrichment, which has remained in the cooling pool for five years. The k eff, hardening spectrum, and the Fuel evolution during burnup were evaluated. This study was performed by using the SCALE 6.0 code.

  • Micro Heteregeneous Approaches for the Insertion of Reprocessed and Combined Thorium Fuel Cycles in a PWR System
    MRS Online Proceedings Library, 2016
    Co-Authors: Fabiana. B. A. Monteiro, Rochkhudson. B. Faria, Ângela Fortini, Clarysson A. M. Da Silva, Victor F. Castro, Claubia Pereira
    Abstract:

    A micro heteregenous Reprocessed Fuel spiked with thorium in a PWR Fuel element considering (TRU-Th) cycle was simulated using three different configurations and different fissile materials that varied from 6.0% to 7.0%. The Reprocessed Fuels were obtained using the ORIGEN 2.1 code from a burned PWR standard Fuel (33,000 MWd/tHM burned), with 3.1% of initial enrichment, which was remained in the cooling pool for five years and then Reprocessed using UREX+ technique. The k_eff and plutonium generation during the burnup were evaluated and compared with the standard Fuel. This study was performed using the SCALE 6.0.

A.l. Costa - One of the best experts on this subject based on the ideXlab platform.

  • Thorium and Transuranic (TRU) Advanced Fuel Cycle: An Option for Brazilian Nuclear Plants
    Thorium Energy for the World, 2016
    Co-Authors: Fabiana. B. A. Monteiro, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, Rochkhudson. B. Faria, Ângela Fortini, Diego M. De Almeida, A.l. Costa
    Abstract:

    A typical pressurised water reactor (PWR) Fuel element containing TRU–Th Fuel cycle was simulated. The study analysed the behaviour of thorium insertion spiked with Reprocessed Fuel by considering different enrichments that varied from 5.5 to 7.0 %. The Reprocessed Fuels were obtained by using the ORIGEN 2.1 code from a burnt PWR standard Fuel (33,000 MWd/tHM burned), with 3.1 % of initial enrichment, which has remained in the cooling pool for five years. The k eff, hardening spectrum, and the Fuel evolution during burnup were evaluated. This study was performed by using the SCALE 6.0 code.

  • GANEX and UREX+ Reprocessed Fuels in ADS
    International Journal of Hydrogen Energy, 2016
    Co-Authors: Graiciany De P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, A.l. Costa
    Abstract:

    Abstract The aim of this study was to compare the neutronic behavior of the Accelerator Driven Systems (ADS) core using Reprocessed Fuel and thorium. The Fuel used in some rods was 232 ThO 2 for U-233 production. In the other rods, two different Reprocessed Fuels were used. One of the studied Fuels was a mixture based upon Pu-MA, removed from PWR-spent Fuel, theoretically Reprocessed by GANEX reprocessing and spiked with 50% of thorium. The other Fuel was a Reprocessed Fuel obtained theoretically from UREX+ (Uranium Extraction) process and spiked with 50% of thorium. Monteburns 2.0 (MCNP5/ORIGEN 2.1) code was used to simulate the neutronic aspects of the Fuels. The results indicated that the use of GANEX or UREX+ Fuel spiked with thorium allowed 233 U production and reduction of high radiotoxicity isotopes.

  • Thorium and Reprocessed Fuel utilization in an accelerator-driven system
    Annals of Nuclear Energy, 2015
    Co-Authors: Graiciany De P. Barros, Maria Auxiliadora F. Veloso, C. Pereira, A.l. Costa
    Abstract:

    Abstract The aim of this study is to investigate the nuclear Fuel evolution and the neutronic parameters of a lead-cooled ADS used for Fuel breeding and transmutation of Reprocessed Fuel. The Fuel used in some rods was 232 ThO 2 for 233 U production. In the other rods, a mixture based upon Pu-MA was used. It was obtained from PWR-spent Fuel, Reprocessed by GANEX, and finally spiked with thorium or depleted uranium. In order to simulate the neutronic aspects, Monteburns 2.0 code (MCNP/ORIGEN 2.1) was used. The results indicated that the simultaneous use of 232 ThO 2 and Reprocessed Fuel allowed the 233 U production without initial requirement of 233 U enrichment and the reduction in the amount of high radiotoxicity isotopes from Reprocessed Fuel.

  • Evaluation of subcritical hybrid systems loaded with Reprocessed Fuel
    Annals of Nuclear Energy, 2015
    Co-Authors: Carlos E. Velasquez, Claubia Pereira, Maria Auxiliadora F. Veloso, Graiciany De P. Barros, A.l. Costa
    Abstract:

    Abstract Two subcritical hybrid systems containing spent Fuel Reprocessed by Ganex technique and spiked with thorium were submitted to neutron irradiation of two different sources: ADS (Accelerator-driven subcritical) and Fusion. The aim is to investigate the nuclear Fuel evolution using Reprocessed Fuel and the neutronic parameters under neutron irradiation. The source multiplication factor and Fuel depletion for both systems were analysed during 10 years. The simulations were performed using MONTEBURNS code (MCNP/ORIGEN). The results indicate the main differences when irradiating the Fuel with different neutron sources as well as the most suitable system for achieving transmutation.

  • Depletion evaluation of an ADS using Reprocessed Fuel
    International Journal of Hydrogen Energy, 2015
    Co-Authors: Graiciany De P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, A.l. Costa
    Abstract:

    Abstract The aim of this study was to investigate the nuclear Fuel evolution and the neutronic parameters of a lead-cooled Accelerator-Driven Systems (ADS) used for Fuel breeding and transmutation of spent Fuel. The simulated core was a cylinder Fueled with a hexagonal lattice with 156 Fuel rods. The Fuel used was a mixture based upon Pu-MA, removed from PWR-spent Fuel, Reprocessed by GANEX and spiked with 82% of thorium. Monteburns 2.0 (MCNP5/ORIGEN 2.1) code was used to simulate the neutronic aspects of the Fuel. The multiplication factor, neutron spectra and nuclear Fuel evolution were analyzed during 10 years of burn-up. The results indicated that the use of GANEX Fuel spiked with thorium allowed 233U production and reduction in the amount of high radiotoxicity isotopes.

Maria Auxiliadora F. Veloso - One of the best experts on this subject based on the ideXlab platform.

  • Criticality safety analysis of spent Fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 Fuels
    Brazilian Journal of Radiation Sciences, 2019
    Co-Authors: Claubia Pereira, Victor Faria De Castro, Jéssica P. Achilles, Fabiano Pereira Cardoso, Maria Auxiliadora F. Veloso
    Abstract:

    A spent Fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses Reprocessed Fuels. PWR nuclear Fuel assemblies with four types of Fuels were considered: standard PWR Fuel, MOX Fuel, thorium-uranium Fuel and Reprocessed transuranic Fuel spiked with thorium. The MOX and UO 2 benchmark model was evaluated using SCALE 6.0 code with KENO-V transport code and then, adopted as a reference for other Fuels compositions. The four Fuel assemblies were submitted to irradiation at normal operation conditions. The burnup calculations were obtained using the TRITON sequence in the SCALE 6.0 code package. The Fuel assemblies modeled use a benchmark 17x17 PWR Fuel assembly dimensions. After irradiation, the Fuels were inserted in the pool. The criticality safety limits were performed using the KENO-V transport code in the CSAS5 sequence. It was shown that mixing a quarter of Reprocessed Fuel withUO 2 Fuel in the pool, it would not need to be resized

  • Thorium and Transuranic (TRU) Advanced Fuel Cycle: An Option for Brazilian Nuclear Plants
    Thorium Energy for the World, 2016
    Co-Authors: Fabiana. B. A. Monteiro, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, Rochkhudson. B. Faria, Ângela Fortini, Diego M. De Almeida, A.l. Costa
    Abstract:

    A typical pressurised water reactor (PWR) Fuel element containing TRU–Th Fuel cycle was simulated. The study analysed the behaviour of thorium insertion spiked with Reprocessed Fuel by considering different enrichments that varied from 5.5 to 7.0 %. The Reprocessed Fuels were obtained by using the ORIGEN 2.1 code from a burnt PWR standard Fuel (33,000 MWd/tHM burned), with 3.1 % of initial enrichment, which has remained in the cooling pool for five years. The k eff, hardening spectrum, and the Fuel evolution during burnup were evaluated. This study was performed by using the SCALE 6.0 code.

  • GANEX and UREX+ Reprocessed Fuels in ADS
    International Journal of Hydrogen Energy, 2016
    Co-Authors: Graiciany De P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, A.l. Costa
    Abstract:

    Abstract The aim of this study was to compare the neutronic behavior of the Accelerator Driven Systems (ADS) core using Reprocessed Fuel and thorium. The Fuel used in some rods was 232 ThO 2 for U-233 production. In the other rods, two different Reprocessed Fuels were used. One of the studied Fuels was a mixture based upon Pu-MA, removed from PWR-spent Fuel, theoretically Reprocessed by GANEX reprocessing and spiked with 50% of thorium. The other Fuel was a Reprocessed Fuel obtained theoretically from UREX+ (Uranium Extraction) process and spiked with 50% of thorium. Monteburns 2.0 (MCNP5/ORIGEN 2.1) code was used to simulate the neutronic aspects of the Fuels. The results indicated that the use of GANEX or UREX+ Fuel spiked with thorium allowed 233 U production and reduction of high radiotoxicity isotopes.

  • Thorium and Reprocessed Fuel utilization in an accelerator-driven system
    Annals of Nuclear Energy, 2015
    Co-Authors: Graiciany De P. Barros, Maria Auxiliadora F. Veloso, C. Pereira, A.l. Costa
    Abstract:

    Abstract The aim of this study is to investigate the nuclear Fuel evolution and the neutronic parameters of a lead-cooled ADS used for Fuel breeding and transmutation of Reprocessed Fuel. The Fuel used in some rods was 232 ThO 2 for 233 U production. In the other rods, a mixture based upon Pu-MA was used. It was obtained from PWR-spent Fuel, Reprocessed by GANEX, and finally spiked with thorium or depleted uranium. In order to simulate the neutronic aspects, Monteburns 2.0 code (MCNP/ORIGEN 2.1) was used. The results indicated that the simultaneous use of 232 ThO 2 and Reprocessed Fuel allowed the 233 U production without initial requirement of 233 U enrichment and the reduction in the amount of high radiotoxicity isotopes from Reprocessed Fuel.

  • Evaluation of subcritical hybrid systems loaded with Reprocessed Fuel
    Annals of Nuclear Energy, 2015
    Co-Authors: Carlos E. Velasquez, Claubia Pereira, Maria Auxiliadora F. Veloso, Graiciany De P. Barros, A.l. Costa
    Abstract:

    Abstract Two subcritical hybrid systems containing spent Fuel Reprocessed by Ganex technique and spiked with thorium were submitted to neutron irradiation of two different sources: ADS (Accelerator-driven subcritical) and Fusion. The aim is to investigate the nuclear Fuel evolution using Reprocessed Fuel and the neutronic parameters under neutron irradiation. The source multiplication factor and Fuel depletion for both systems were analysed during 10 years. The simulations were performed using MONTEBURNS code (MCNP/ORIGEN). The results indicate the main differences when irradiating the Fuel with different neutron sources as well as the most suitable system for achieving transmutation.

Takanori Kitada - One of the best experts on this subject based on the ideXlab platform.

  • seed and blanket ads using thorium Reprocessed Fuel parametric survey on tru transmutation performance and safety characteristics
    Annals of Nuclear Energy, 2015
    Co-Authors: Takanori Kitada
    Abstract:

    Abstract Conceptual designs of accelerator driven systems (ADS) that utilize thorium Fuel as blanket and Reprocessed Fuel as seed for fission reaction in order to transmute the transuranic elements in spent nuclear Fuel and produce energy from thorium utilization was proposed. In order to analyze the TRU transmutation performance of the system while the safety margin during the operation is satisfied, a parametric survey is done in this study. The impact of minor actinide (MA) amount and the reactor size on transmutation efficiency and safety characteristics of the ADS is investigated using MCNPX code using the ENDF/B-VII. As the results, with increasing MA content, TRU transmutation rate is increased while void reactivity of the system becomes less negative. Besides, increasing the core size by introducing more thorium and Reprocessed Fuel assemblies into the system reduces the TRU transmutation rate and reactivity swing due to burnup of the system. In order to match the efficient transmutation purpose and safety features during operation, higher MA content is suggested to introduce into the system.

  • Seed and blanket thorium-Reprocessed Fuel ADS: Multi-cycle approach for higher thorium utilization and TRU transmutation
    Annals of Nuclear Energy, 2015
    Co-Authors: Takanori Kitada
    Abstract:

    Abstract In the previous publication, the seed and blanket thorium-Reprocessed Fuel ADS was designed for efficient transmutation of TRU waste from the spent nuclear Fuel. In this study, the multi-cycle core was designed in order to increase thorium utilization and TRU waste transmutation. For that purpose, the Reprocessed Fuel assemblies inside the subcritical core are shuffled for twice burnt while the thorium assemblies are remained inside the reactor until the end of reactor life. As the result, at the equilibrium state, the thorium Fuel contribution to total core power is improved (35.7%) compared to the startup cycle and it has benefit in flattening the power peaking inside the subcritical core. Compare to the startup cycle, less Reprocessed Fuel is loaded but the Reprocessed assemblies are shuffled and burnt twice, hence, the TRUs are transmuted in a deeper level. At discharge, the reduction of radiotoxicity from the TRU waste is about 20% with 1% uncertainty, mainly due to the reduction of Pu and Am.

  • Seed and blanket ADS using thorium–Reprocessed Fuel: Parametric survey on TRU transmutation performance and safety characteristics
    Annals of Nuclear Energy, 2015
    Co-Authors: Takanori Kitada
    Abstract:

    Abstract Conceptual designs of accelerator driven systems (ADS) that utilize thorium Fuel as blanket and Reprocessed Fuel as seed for fission reaction in order to transmute the transuranic elements in spent nuclear Fuel and produce energy from thorium utilization was proposed. In order to analyze the TRU transmutation performance of the system while the safety margin during the operation is satisfied, a parametric survey is done in this study. The impact of minor actinide (MA) amount and the reactor size on transmutation efficiency and safety characteristics of the ADS is investigated using MCNPX code using the ENDF/B-VII. As the results, with increasing MA content, TRU transmutation rate is increased while void reactivity of the system becomes less negative. Besides, increasing the core size by introducing more thorium and Reprocessed Fuel assemblies into the system reduces the TRU transmutation rate and reactivity swing due to burnup of the system. In order to match the efficient transmutation purpose and safety features during operation, higher MA content is suggested to introduce into the system.

  • Transmutation Strategy Using Thorium-Reprocessed Fuel ADS for Future Reactors in Vietnam
    Science and Technology of Nuclear Installations, 2013
    Co-Authors: Takanori Kitada
    Abstract:

    Nuclear power is believed to be a key to the energy security for a developing country like Vietnam where the power demanding increases rapidly every year. Nevertheless, spent nuclear Fuel from nuclear power plants is the source of radiotoxic and proliferation risk. A conceptual design of ADS utilizing thorium Fuel as a based Fuel and Reprocessed Fuel as a seed for nuclear waste transmutation and energy production is proposed as one of the clean, safe, and economical solutions for the problem. In the design, 96 seed assemblies and 84 blanket assemblies were inserted into the core to make a heterogeneous subcritical core configuration. Introducing thorium Fuel into the core offers an effective way to transmute plutonium and minor actinide (MA) and gain energy from this process. Transmutation rate as a function of burnup is estimated using MCNPX 2.7.0 code. Results show that by using the seed-blanket designed ADS, at 40 GWd/t burnup, 192 kg of plutonium and 156 kg of MA can be eliminated. Equivalently, 1  ADS can be able to transmute the transuranic (TRU) waste from 2  LWRs. 14 units of ADS would be required to eliminate TRUs from the future reactors to be constructed in Vietnam.

Graiciany De P. Barros - One of the best experts on this subject based on the ideXlab platform.

  • GANEX and UREX+ Reprocessed Fuels in ADS
    International Journal of Hydrogen Energy, 2016
    Co-Authors: Graiciany De P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, A.l. Costa
    Abstract:

    Abstract The aim of this study was to compare the neutronic behavior of the Accelerator Driven Systems (ADS) core using Reprocessed Fuel and thorium. The Fuel used in some rods was 232 ThO 2 for U-233 production. In the other rods, two different Reprocessed Fuels were used. One of the studied Fuels was a mixture based upon Pu-MA, removed from PWR-spent Fuel, theoretically Reprocessed by GANEX reprocessing and spiked with 50% of thorium. The other Fuel was a Reprocessed Fuel obtained theoretically from UREX+ (Uranium Extraction) process and spiked with 50% of thorium. Monteburns 2.0 (MCNP5/ORIGEN 2.1) code was used to simulate the neutronic aspects of the Fuels. The results indicated that the use of GANEX or UREX+ Fuel spiked with thorium allowed 233 U production and reduction of high radiotoxicity isotopes.

  • Thorium and Reprocessed Fuel utilization in an accelerator-driven system
    Annals of Nuclear Energy, 2015
    Co-Authors: Graiciany De P. Barros, Maria Auxiliadora F. Veloso, C. Pereira, A.l. Costa
    Abstract:

    Abstract The aim of this study is to investigate the nuclear Fuel evolution and the neutronic parameters of a lead-cooled ADS used for Fuel breeding and transmutation of Reprocessed Fuel. The Fuel used in some rods was 232 ThO 2 for 233 U production. In the other rods, a mixture based upon Pu-MA was used. It was obtained from PWR-spent Fuel, Reprocessed by GANEX, and finally spiked with thorium or depleted uranium. In order to simulate the neutronic aspects, Monteburns 2.0 code (MCNP/ORIGEN 2.1) was used. The results indicated that the simultaneous use of 232 ThO 2 and Reprocessed Fuel allowed the 233 U production without initial requirement of 233 U enrichment and the reduction in the amount of high radiotoxicity isotopes from Reprocessed Fuel.

  • Evaluation of subcritical hybrid systems loaded with Reprocessed Fuel
    Annals of Nuclear Energy, 2015
    Co-Authors: Carlos E. Velasquez, Claubia Pereira, Maria Auxiliadora F. Veloso, Graiciany De P. Barros, A.l. Costa
    Abstract:

    Abstract Two subcritical hybrid systems containing spent Fuel Reprocessed by Ganex technique and spiked with thorium were submitted to neutron irradiation of two different sources: ADS (Accelerator-driven subcritical) and Fusion. The aim is to investigate the nuclear Fuel evolution using Reprocessed Fuel and the neutronic parameters under neutron irradiation. The source multiplication factor and Fuel depletion for both systems were analysed during 10 years. The simulations were performed using MONTEBURNS code (MCNP/ORIGEN). The results indicate the main differences when irradiating the Fuel with different neutron sources as well as the most suitable system for achieving transmutation.

  • Depletion evaluation of an ADS using Reprocessed Fuel
    International Journal of Hydrogen Energy, 2015
    Co-Authors: Graiciany De P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Carlos E. Velasquez, A.l. Costa
    Abstract:

    Abstract The aim of this study was to investigate the nuclear Fuel evolution and the neutronic parameters of a lead-cooled Accelerator-Driven Systems (ADS) used for Fuel breeding and transmutation of spent Fuel. The simulated core was a cylinder Fueled with a hexagonal lattice with 156 Fuel rods. The Fuel used was a mixture based upon Pu-MA, removed from PWR-spent Fuel, Reprocessed by GANEX and spiked with 82% of thorium. Monteburns 2.0 (MCNP5/ORIGEN 2.1) code was used to simulate the neutronic aspects of the Fuel. The multiplication factor, neutron spectra and nuclear Fuel evolution were analyzed during 10 years of burn-up. The results indicated that the use of GANEX Fuel spiked with thorium allowed 233U production and reduction in the amount of high radiotoxicity isotopes.

  • Study of an ADS Loaded with Thorium and Reprocessed Fuel
    Science and Technology of Nuclear Installations, 2012
    Co-Authors: Graiciany De P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, A.l. Costa
    Abstract:

    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 was for production. 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 of without the initial requirement of enrichment. 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 () 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 of and Reprocessed Fuel allowed production without the initial requirement of enrichment.