The Experts below are selected from a list of 207 Experts worldwide ranked by ideXlab platform
Hiroshi Sekimoto - One of the best experts on this subject based on the ideXlab platform.
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Optimization of Small Long Life Gas Cooled Fast Reactors With Natural Uranium as Fuel Cycle Input
2016Co-Authors: Menik Ariani, Abdul Waris, Fiber Monado, I. Arif, Ferhat A, Hiroshi SekimotoAbstract:Abstract. In this study gas cooled reactor system are combined with modified CANDLE burn-up scheme to create small long life fast reactors with Natural circulation as fuel cycle input. Such system can utilize Natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore using this type of nuclear power plants optimum nuclear energy utilization including in developing countries can be easily conducted without the problem of nuclear proliferation. In this paper, optimization of Small and Medium Long-life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input has been performed. The optimization processes include adjustment of fuel region movement scheme, volume fraction adjustment, core dimension, etc. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 75 W/cc. With such condition we investigated small and medium sized cores from 300 MWt to 600 MWt with all being operated for 10 years without refueling and fuel shuffling and just need Natural Uranium as fuel cycle input. The average discharge burn-up is about in the range of 23-30 % HM
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The study of capability Natural Uranium as fuel cycle input for long life gas cooled fast reactors with helium as coolant
2016Co-Authors: Menik Ariani, Zaki Su’ud, Fiber Monado, Octavianus Cakra Satya, Hiroshi SekimotoAbstract:The objective of the present research is to assess the feasibility design of small long-life Gas Cooled Fast Reactor with helium as coolant. GCFR included in the Generation-IV reactor systems are being developed to provide sustainable energy resources that meet future energy demand in a reliable, safe, and proliferation-resistant manner. This reactor can be operated without enrichment and reprocessing forever, once it starts. To obtain the capability of consuming Natural Uranium as fuel cycle input modified CANDLE burn-up scheme was adopted in this system with different core design. This study has compared the core with three designs of core reactors with the same thermal power 600 MWth. The fuel composition each design was arranged by divided core into several parts of equal volume axially i.e. 6, 8 and 10 parts related to material burn-up history. The fresh Natural Uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of the region (i) into region (i+1) region after the end of 10 years burn-up cycle. The calculation results shows that for the burn-up strategy on “Region-8” and “Region-10” core designs, after the reactors start-up the operation furthermore they only needs Natural Uranium supply to the next life operation until one period of refueling (10 years).The objective of the present research is to assess the feasibility design of small long-life Gas Cooled Fast Reactor with helium as coolant. GCFR included in the Generation-IV reactor systems are being developed to provide sustainable energy resources that meet future energy demand in a reliable, safe, and proliferation-resistant manner. This reactor can be operated without enrichment and reprocessing forever, once it starts. To obtain the capability of consuming Natural Uranium as fuel cycle input modified CANDLE burn-up scheme was adopted in this system with different core design. This study has compared the core with three designs of core reactors with the same thermal power 600 MWth. The fuel composition each design was arranged by divided core into several parts of equal volume axially i.e. 6, 8 and 10 parts related to material burn-up history. The fresh Natural Uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh n...
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Conceptual design study on very small long-life gas cooled fast reactor using metallic Natural Uranium-Zr as fuel cycle input
2014Co-Authors: Fiber Monado, Menik Ariani, Zaki Su’ud, Abdul Waris, Ferhat Aziz, Khairul Basar, Sidik Permana, Hiroshi SekimotoAbstract:A conceptual design study of very small 350 MWth Gas-cooled Fast Reactors with Helium coolant has been performed. In this study Modified CANDLE burn-up scheme was implemented to create small and long life fast reactors with Natural Uranium as fuel cycle input. Such system can utilize Natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. The core with metallic fuel based was subdivided into 10 regions with the same volume. The fresh Natural Uranium is initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all axial regions. The reactor discharge burn-up is 31.8% HM. From the neutronic point of view, this design is in compliance with good performance.
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The prospect of gas cooled fast reactors for long life reactors with Natural Uranium as fuel cycle input
Annals of Nuclear Energy, 2013Co-Authors: Zaki Su’ud, Hiroshi SekimotoAbstract:Abstract Gas cooled fast reactors are among the Generation 4 nuclear power plants (NPPs) with hard neutron spectrum characteristics which can be utilized to create power reactors with high breeding/conversion ratio capability. In this study the gas cooled reactor system is combined with modified CANDLE burn-up scheme to create long life fast reactors with Natural Uranium as fuel cycle input. Such a system can utilize Natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore, by using this type of nuclear power plants optimum nuclear energy utilization, including in developing countries, can be easily obtained without the problem of nuclear proliferation. In this paper, a design study of 800 MWt long-life gas cooled fast reactors with Natural Uranium as fuel cycle input has been performed. Due to the thermal hydraulic constraints, the average power density of the proposed design is limited to 70 W/cc. The system has excellent performance and is at least comparable to that of Pb–Bi cooled system. The average discharge burn-up is about 258 GWd/ton HM.
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Desain Study of Pb-Bi Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input Using Special Shuffling Strategy in Radial Direction
Advanced Materials Research, 2013Co-Authors: Zaki Su’ud, Hiroshi Sekimoto, Feriska Handayani Irka, Taufiq Imam, P. SidikAbstract:Design study of Pb-Bi cooled fast reactors with Natural Uranium as fuel cycle input using special radial shuffling strategy has been performed. The reactors utilizes UN-PUN as fuel, Eutectic Pb-Bi as coolant, and can be operated without refueling for 10 years in each batch. Reactor design optimization is performed to utilize Natural Uranium as fuel cycle input. This reactor subdivided into 6 regions with equal volume in radial directions. The Natural Uranium is initially put in region 1, and after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all regions. The calculation has been done by using SRAC-Citation system code and JENDL-3.2 library. The effective multiplication factor change increases monotonously during 10 years reactor operation time. There is significant power distribution change in the central part of the core during the BOC and the EOC. It is larger than that in the case of modified CANDLE case which use axial direction burning region move. The burnup level of fuel is slowly grows during the first 15 years but then grow fastly in the rest of burnup history. This pattern is a little bit different from the case of modified CANDLE burnup scheme in Axial direction in which the slow growing burnup period is relatively longer almost half of the burnup history.
Zaki Su’ud - One of the best experts on this subject based on the ideXlab platform.
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The study of capability Natural Uranium as fuel cycle input for long life gas cooled fast reactors with helium as coolant
2016Co-Authors: Menik Ariani, Zaki Su’ud, Fiber Monado, Octavianus Cakra Satya, Hiroshi SekimotoAbstract:The objective of the present research is to assess the feasibility design of small long-life Gas Cooled Fast Reactor with helium as coolant. GCFR included in the Generation-IV reactor systems are being developed to provide sustainable energy resources that meet future energy demand in a reliable, safe, and proliferation-resistant manner. This reactor can be operated without enrichment and reprocessing forever, once it starts. To obtain the capability of consuming Natural Uranium as fuel cycle input modified CANDLE burn-up scheme was adopted in this system with different core design. This study has compared the core with three designs of core reactors with the same thermal power 600 MWth. The fuel composition each design was arranged by divided core into several parts of equal volume axially i.e. 6, 8 and 10 parts related to material burn-up history. The fresh Natural Uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of the region (i) into region (i+1) region after the end of 10 years burn-up cycle. The calculation results shows that for the burn-up strategy on “Region-8” and “Region-10” core designs, after the reactors start-up the operation furthermore they only needs Natural Uranium supply to the next life operation until one period of refueling (10 years).The objective of the present research is to assess the feasibility design of small long-life Gas Cooled Fast Reactor with helium as coolant. GCFR included in the Generation-IV reactor systems are being developed to provide sustainable energy resources that meet future energy demand in a reliable, safe, and proliferation-resistant manner. This reactor can be operated without enrichment and reprocessing forever, once it starts. To obtain the capability of consuming Natural Uranium as fuel cycle input modified CANDLE burn-up scheme was adopted in this system with different core design. This study has compared the core with three designs of core reactors with the same thermal power 600 MWth. The fuel composition each design was arranged by divided core into several parts of equal volume axially i.e. 6, 8 and 10 parts related to material burn-up history. The fresh Natural Uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh n...
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Conceptual design study on very small long-life gas cooled fast reactor using metallic Natural Uranium-Zr as fuel cycle input
2014Co-Authors: Fiber Monado, Menik Ariani, Zaki Su’ud, Abdul Waris, Ferhat Aziz, Khairul Basar, Sidik Permana, Hiroshi SekimotoAbstract:A conceptual design study of very small 350 MWth Gas-cooled Fast Reactors with Helium coolant has been performed. In this study Modified CANDLE burn-up scheme was implemented to create small and long life fast reactors with Natural Uranium as fuel cycle input. Such system can utilize Natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. The core with metallic fuel based was subdivided into 10 regions with the same volume. The fresh Natural Uranium is initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all axial regions. The reactor discharge burn-up is 31.8% HM. From the neutronic point of view, this design is in compliance with good performance.
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Design of Gas-Cooled Fast Reactor 600MWth with Natural Uranium As Fuel Circle Input
Jurnal ILMU DASAR, 2013Co-Authors: Menik Ariani, Zaki Su’ud, Fiber MonadoAbstract:This article presents the conceptual design of gas-cooled fast reactor (helium), the small size of the long-lived 600 MWth. Early stages of the design is to determine the geometry of the terrace, the value of the volume fraction and the mass fraction of fuel, cladding and coolant structure to calculate the parameters of reactivity, burnup, power distribution and density changes nuclides U238 and Pu239. The calculation is done using SRAC-CITATION code. SRAC code with JENDL-3.2 Data nuclides produced macroscopic cross section values for the eight energy group. Multi-group numerical solution of diffusion equations for 2-D geometry terrace RZ performed by CITATION code. The study results showed that the scheme Modified CANDLE, thermal power output is 600 MWth, with a fuel cycle for 10 years. This reactor has the advantage of requiring only the input of Natural Uranium in the fuel cycle, without the need for enrichment processes that affect the economic value. Keywords : Reactor, Natural Uranium, modified candle, burnup
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The prospect of gas cooled fast reactors for long life reactors with Natural Uranium as fuel cycle input
Annals of Nuclear Energy, 2013Co-Authors: Zaki Su’ud, Hiroshi SekimotoAbstract:Abstract Gas cooled fast reactors are among the Generation 4 nuclear power plants (NPPs) with hard neutron spectrum characteristics which can be utilized to create power reactors with high breeding/conversion ratio capability. In this study the gas cooled reactor system is combined with modified CANDLE burn-up scheme to create long life fast reactors with Natural Uranium as fuel cycle input. Such a system can utilize Natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore, by using this type of nuclear power plants optimum nuclear energy utilization, including in developing countries, can be easily obtained without the problem of nuclear proliferation. In this paper, a design study of 800 MWt long-life gas cooled fast reactors with Natural Uranium as fuel cycle input has been performed. Due to the thermal hydraulic constraints, the average power density of the proposed design is limited to 70 W/cc. The system has excellent performance and is at least comparable to that of Pb–Bi cooled system. The average discharge burn-up is about 258 GWd/ton HM.
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Desain Study of Pb-Bi Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input Using Special Shuffling Strategy in Radial Direction
Advanced Materials Research, 2013Co-Authors: Zaki Su’ud, Hiroshi Sekimoto, Feriska Handayani Irka, Taufiq Imam, P. SidikAbstract:Design study of Pb-Bi cooled fast reactors with Natural Uranium as fuel cycle input using special radial shuffling strategy has been performed. The reactors utilizes UN-PUN as fuel, Eutectic Pb-Bi as coolant, and can be operated without refueling for 10 years in each batch. Reactor design optimization is performed to utilize Natural Uranium as fuel cycle input. This reactor subdivided into 6 regions with equal volume in radial directions. The Natural Uranium is initially put in region 1, and after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all regions. The calculation has been done by using SRAC-Citation system code and JENDL-3.2 library. The effective multiplication factor change increases monotonously during 10 years reactor operation time. There is significant power distribution change in the central part of the core during the BOC and the EOC. It is larger than that in the case of modified CANDLE case which use axial direction burning region move. The burnup level of fuel is slowly grows during the first 15 years but then grow fastly in the rest of burnup history. This pattern is a little bit different from the case of modified CANDLE burnup scheme in Axial direction in which the slow growing burnup period is relatively longer almost half of the burnup history.
W. H. Trzaska - One of the best experts on this subject based on the ideXlab platform.
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Measurements of nuclide yields in neutron-induced fission of Natural Uranium for SPIRAL2
Hyperfine Interactions, 2012Co-Authors: G. Lhersonneau, T. Malkiewicz, W. H. TrzaskaAbstract:Cross-sections for nuclide production in fast-neutron induced fission of Natural Uranium are part of the input for predictions of yields of neutron-rich nuclides obtainable at Radioactive Ion Beam facilities. We first describe the neutron spectra produced according to the scheme once envisaged for SPES (protons on an enriched 13C target) and the one adopted for SPIRAL2 (deuterons on Natural carbon), which both have been measured at JYFL.We then present the measurements of Z-splits in isobaric chains performed at IGISOL. When coupled with the fission cross-section and A-splits for the relevant neutron spectrum, they allow estimates of nuclide crosssections. It looks that calculations
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Measurements of nuclide yields in neutron-induced fission of Natural Uranium for SPIRAL2
Three decades of research using IGISOL technique at the University of Jyväskylä, 2012Co-Authors: G. Lhersonneau, T. Malkiewicz, W. H. TrzaskaAbstract:Cross-sections for nuclide production in fast-neutron induced fission of Natural Uranium are part of the input for predictions of yields of neutron-rich nuclides obtainable at Radioactive Ion Beam facilities. We first describe the neutron spectra produced according to the scheme once envisaged for SPES (protons on an enriched13C target) and the one adopted for SPIRAL2 (deuterons on Natural carbon), which both have been measured at JYFL.We then present the measurements of Z-splits in isobaric chains performed at IGISOL. When coupled with the fission cross-section and A-splits for the relevant neutron spectrum, they allow estimates of nuclide crosssections. It looks that calculations, even those based on modern libraries, are too optimistic by about a factor of two
J.c. Lozano - One of the best experts on this subject based on the ideXlab platform.
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Elimination of Natural Uranium and 226Ra from contaminated waters by rhizofiltration using Helianthus annuus L
Science of The Total Environment, 2008Co-Authors: F. Vera Tomé, P. Blanco Rodríguez, J.c. LozanoAbstract:The elimination of Natural Uranium and (226)Ra from contaminated waters by rhizofiltration was tested using Helianthus annuus L. (sunflower) seedlings growing in a hydroponic medium. Different experiments were designed to determine the optimum age of the seedlings for the remediation process, and also to study the principal way in which the radionuclides are removed from the solution by the sunflower roots. In every trial a precipitate appeared which contained a major fraction of the Natural Uranium and (226)Ra. The results indicated that the seedlings themselves induced the formation of this precipitate. When four-week-old seedlings were exposed to contaminated water, a period of only 2 days was sufficient to remove the Natural Uranium and (226)Ra from the solution: about 50% of the Natural Uranium and 70% of the (226)Ra were fixed in the roots, and essentially the rest was found in the precipitate, with only very small percentages fixed in the shoots and left in solution.
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Elimination of Natural Uranium and (226)Ra from contaminated waters by rhizofiltration using Helianthus annuus L.
The Science of the total environment, 2008Co-Authors: F. Vera Tomé, P. Blanco Rodríguez, J.c. LozanoAbstract:The elimination of Natural Uranium and (226)Ra from contaminated waters by rhizofiltration was tested using Helianthus annuus L. (sunflower) seedlings growing in a hydroponic medium. Different experiments were designed to determine the optimum age of the seedlings for the remediation process, and also to study the principal way in which the radionuclides are removed from the solution by the sunflower roots. In every trial a precipitate appeared which contained a major fraction of the Natural Uranium and (226)Ra. The results indicated that the seedlings themselves induced the formation of this precipitate. When four-week-old seedlings were exposed to contaminated water, a period of only 2 days was sufficient to remove the Natural Uranium and (226)Ra from the solution: about 50% of the Natural Uranium and 70% of the (226)Ra were fixed in the roots, and essentially the rest was found in the precipitate, with only very small percentages fixed in the shoots and left in solution.
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Linearity assumption in soil-to-plant transfer factors of Natural Uranium and radium in Helianthus annuus L.
The Science of the total environment, 2005Co-Authors: P. Blanco Rodríguez, F. Vera Tomé, M Pérez Fernández, J.c. LozanoAbstract:The linearity assumption of the validation of soil-to-plant transfer factors of Natural Uranium and (226)Ra was tested using Helianthus annuus L. (sunflower) grown in a hydroponic medium. Transfer of Natural Uranium and (226)Ra was tested in both the aerial fraction of plants and in the overall seedlings (roots and shoots). The results show that the linearity assumption can be considered valid in the hydroponic growth of sunflowers for the radionuclides studied. The ability of sunflowers to translocate Uranium and (226)Ra was also investigated, as well as the feasibility of using sunflower plants to remove Uranium and radium from contaminated water, and by extension, their potential for phytoextraction. In this sense, the removal percentages obtained for Natural Uranium and (226)Ra were 24% and 42%, respectively. Practically all the Uranium is accumulated in the roots. However, 86% of the (226)Ra activity concentration in roots was translocated to the aerial part.
Menik Ariani - One of the best experts on this subject based on the ideXlab platform.
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Optimization of Small Long Life Gas Cooled Fast Reactors With Natural Uranium as Fuel Cycle Input
2016Co-Authors: Menik Ariani, Abdul Waris, Fiber Monado, I. Arif, Ferhat A, Hiroshi SekimotoAbstract:Abstract. In this study gas cooled reactor system are combined with modified CANDLE burn-up scheme to create small long life fast reactors with Natural circulation as fuel cycle input. Such system can utilize Natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore using this type of nuclear power plants optimum nuclear energy utilization including in developing countries can be easily conducted without the problem of nuclear proliferation. In this paper, optimization of Small and Medium Long-life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input has been performed. The optimization processes include adjustment of fuel region movement scheme, volume fraction adjustment, core dimension, etc. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 75 W/cc. With such condition we investigated small and medium sized cores from 300 MWt to 600 MWt with all being operated for 10 years without refueling and fuel shuffling and just need Natural Uranium as fuel cycle input. The average discharge burn-up is about in the range of 23-30 % HM
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The study of capability Natural Uranium as fuel cycle input for long life gas cooled fast reactors with helium as coolant
2016Co-Authors: Menik Ariani, Zaki Su’ud, Fiber Monado, Octavianus Cakra Satya, Hiroshi SekimotoAbstract:The objective of the present research is to assess the feasibility design of small long-life Gas Cooled Fast Reactor with helium as coolant. GCFR included in the Generation-IV reactor systems are being developed to provide sustainable energy resources that meet future energy demand in a reliable, safe, and proliferation-resistant manner. This reactor can be operated without enrichment and reprocessing forever, once it starts. To obtain the capability of consuming Natural Uranium as fuel cycle input modified CANDLE burn-up scheme was adopted in this system with different core design. This study has compared the core with three designs of core reactors with the same thermal power 600 MWth. The fuel composition each design was arranged by divided core into several parts of equal volume axially i.e. 6, 8 and 10 parts related to material burn-up history. The fresh Natural Uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of the region (i) into region (i+1) region after the end of 10 years burn-up cycle. The calculation results shows that for the burn-up strategy on “Region-8” and “Region-10” core designs, after the reactors start-up the operation furthermore they only needs Natural Uranium supply to the next life operation until one period of refueling (10 years).The objective of the present research is to assess the feasibility design of small long-life Gas Cooled Fast Reactor with helium as coolant. GCFR included in the Generation-IV reactor systems are being developed to provide sustainable energy resources that meet future energy demand in a reliable, safe, and proliferation-resistant manner. This reactor can be operated without enrichment and reprocessing forever, once it starts. To obtain the capability of consuming Natural Uranium as fuel cycle input modified CANDLE burn-up scheme was adopted in this system with different core design. This study has compared the core with three designs of core reactors with the same thermal power 600 MWth. The fuel composition each design was arranged by divided core into several parts of equal volume axially i.e. 6, 8 and 10 parts related to material burn-up history. The fresh Natural Uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh n...
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Conceptual design study on very small long-life gas cooled fast reactor using metallic Natural Uranium-Zr as fuel cycle input
2014Co-Authors: Fiber Monado, Menik Ariani, Zaki Su’ud, Abdul Waris, Ferhat Aziz, Khairul Basar, Sidik Permana, Hiroshi SekimotoAbstract:A conceptual design study of very small 350 MWth Gas-cooled Fast Reactors with Helium coolant has been performed. In this study Modified CANDLE burn-up scheme was implemented to create small and long life fast reactors with Natural Uranium as fuel cycle input. Such system can utilize Natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. The core with metallic fuel based was subdivided into 10 regions with the same volume. The fresh Natural Uranium is initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all axial regions. The reactor discharge burn-up is 31.8% HM. From the neutronic point of view, this design is in compliance with good performance.
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Design of Gas-Cooled Fast Reactor 600MWth with Natural Uranium As Fuel Circle Input
Jurnal ILMU DASAR, 2013Co-Authors: Menik Ariani, Zaki Su’ud, Fiber MonadoAbstract:This article presents the conceptual design of gas-cooled fast reactor (helium), the small size of the long-lived 600 MWth. Early stages of the design is to determine the geometry of the terrace, the value of the volume fraction and the mass fraction of fuel, cladding and coolant structure to calculate the parameters of reactivity, burnup, power distribution and density changes nuclides U238 and Pu239. The calculation is done using SRAC-CITATION code. SRAC code with JENDL-3.2 Data nuclides produced macroscopic cross section values for the eight energy group. Multi-group numerical solution of diffusion equations for 2-D geometry terrace RZ performed by CITATION code. The study results showed that the scheme Modified CANDLE, thermal power output is 600 MWth, with a fuel cycle for 10 years. This reactor has the advantage of requiring only the input of Natural Uranium in the fuel cycle, without the need for enrichment processes that affect the economic value. Keywords : Reactor, Natural Uranium, modified candle, burnup
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Design of Small Gas Cooled Fast Reactor with Two Region of Natural Uranium Fuel Fraction
2012Co-Authors: Menik Ariani, Hiroshi Sekimoto, Zaki Su’ud, Abdul Waris, Khairurrijal, Fiber Monado, Sinsuke NakayamaAbstract:A design study of small Gas Cooled Fast Reactor with two region fuel has been performed. In this study, design GCFR with Helium coolant which can be continuously operated by supplying mixed Natural Uranium without fuel enrichment plant or fuel reprocessing plant. The active reactor cores are divided into two region fuel i.e. 60% fuel fraction of Natural Uranium as inner core and 65% fuel fraction of Natural Uranium as outer core. Each fuel core regions are subdivided into ten parts (region-1 until region-10) with the same volume in the axial direction. The fresh Natural Uranium initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 filled by fresh Natural Uranium. This concept is basically applied to all regions in both cores area, i.e. shifted the core of ith region into i+1 region after the end of 10 years burn-up cycle. For the next cycles, we will add only Natural Uranium on each region-1. The burn-up calculation is performed using collision probability method PIJ (cell burn-up calculation) in SRAC code which then given eight energy group macroscopic cross section data to be used in two dimensional R-Z geometry multi groups diffusion calculation in CITATION code. This reactor can results power thermal 600 MWth with average power density i.e. 80 watt/cc. After reactor start-up the operation, furthermore reactor only needs Natural Uranium supply for continue operation along 100 years. This calculation result then compared with one region fuel design i.e. 60% and 65% fuel fraction. This core design with two region fuel fraction can be an option for fuel optimization.
