The Experts below are selected from a list of 5739 Experts worldwide ranked by ideXlab platform
Suizheng Qiu - One of the best experts on this subject based on the ideXlab platform.
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development and application of a Neutronics thermal hydraulics coupling optimization code for the cfetr helium cooled solid breeder blanket with mixed pebble beds
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Suizheng QiuAbstract:Abstract As one of the most important components of fusion reactor, breeding blanket mainly accounts for tritium self-sufficiency, shielding and fusion energy collection. The performance of the blanket is mainly determined by the internal structural arrangement and material composition. However, if we directly adopt a three-dimensional calculation model for the blanket design and optimization, not only will it consume extensive human and computer resources, but also make the computational process extremely complicated and lengthy. Considering that the radial arrangement of the functional zones, which has the greatest influence on the performance, is the basis of the detailed and accurate 3D design of the blanket, NTCOC, a N eutronics/ T hermal-hydraulics C oupling O ptimization C ode, which adopts simplified 1D Neutronics and 2D thermal-hydraulic calculation models, is developed for accelerating the radial build design and optimization of the blanket in this work. This code realizes the functions of both the automatic iterative updating the temperature-dependent cross-section libraries and the data transmission between the Neutronics and thermal-hydraulic calculation results through the inner and external coupling between the MCNP4C and CFD software, respectively. Therefore, this can make the comprehensive optimization analyses progress much faster and more accurate. In addition, a variable step length method is adopted to further improve the coupling optimization speed of this code, and several leading design objectives are set as the optimization criteria instead of taking all the possible practical engineering constrains into account. Finally, this code has been applied to optimize the radially arranged zones of a conceptual design scheme of Chinese Fusion Engineering Test Reactor (CFETR) helium cooled solid breeder blanket, which adopts mixed pebble beds as both the tritium breeder and neutron multiplier, under both the normal and critical conditions.
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evaluation and optimization of tritium breeding shielding and nuclear heating performances of the helium cooled solid breeder blanket for cfetr
International Journal of Hydrogen Energy, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Qiang Lian, Suizheng QiuAbstract:Abstract Chinese Fusion Engineering Test Reactor (CFETR) is a new test tokamak device being designed in China aimed to bridge gaps between ITER and DEMO. As one of the candidate tritium breeding blankets, a conceptual design scheme of the helium cooled solid breeder blanket has been proposed and a series of preliminary analyses have been carried out to access the performances. However, both the required global tritium breeding ratio for CFETR not less than 1.2 and its poor working conditions under intense radiation need further thorough Neutronics analyses and optimizations during the design phase. In this work, first, three-dimensional Neutronics model of CFETR was built, and the neutron wall loading and global TBR were obtained. The nuclear and thermal calculation results were automatically coupled, which could make the Neutronics calculation results more accurate and guaranteed they could always satisfy the corresponding thermal limits during the whole process. Then, the tritium breeding and shielding performances of both the outboard and inboard equatorial blanket modules were optimized for the comprehensive optimal schemes. The influences of Be/W armors on the shielding performance and TBR were also investigated. Finally, the nuclear heating rates and the neutron flux densities in different components were calculated based on the obtained comprehensive optimal scheme. In this paper, the Neutronics analyses and optimizations verified that the optimized conceptual design could well meet the tritium self-sufficiency and neutron shielding requirements, and this could provide a valuable reference for the further thermal-hydraulic analysis and structural optimization of the CFETR helium cooled solid breeder blanket.
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steady and transient solutions of Neutronics problems based on finite volume method fvm with a cfd code
Progress in Nuclear Energy, 2015Co-Authors: Dalin Zhang, Wenxi Tian, Kunpeng Wang, Suizheng QiuAbstract:Abstract In recent years, Computational Fluid Dynamics (CFD) methodology has been widely used for solving multi-dimensional thermal-hydraulics problems in nuclear science and engineering. As for the Neutronics analysis, it mostly depends on the deterministic or probabilistic method codes which are independent of the thermal-hydraulic ones. Usually an extra interface program needs to be developed for the data exchange between the two kinds of codes in the coupled calculation. In this paper, a Temporal And Spatial Neutronics Analysis Module (TASNAM) in commercial CFD package FLUENT was developed based on the User Defined Function (UDF) and User Define Scalar (UDS) to solve the Neutronics problems. Neutron diffusion equations and delayed neutron precursors balance equations are discretized by finite volume method (FVM) and can be solved with CFD conservation equations simultaneously. In order to demonstrate the feasibility and accuracy of TASNAM in FLUENT, three Neutronics benchmark problems, the 2D-IAEA, 2D-TWIGL, and 2D-LRA benchmark problem are analyzed. The calculation results in the present paper have a good agreement with the reference values, which demonstrates that the TASNAM in FLUENT can solve Neutronics problems accurately.
Wenxi Tian - One of the best experts on this subject based on the ideXlab platform.
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development and application of a Neutronics thermal hydraulics coupling optimization code for the cfetr helium cooled solid breeder blanket with mixed pebble beds
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Suizheng QiuAbstract:Abstract As one of the most important components of fusion reactor, breeding blanket mainly accounts for tritium self-sufficiency, shielding and fusion energy collection. The performance of the blanket is mainly determined by the internal structural arrangement and material composition. However, if we directly adopt a three-dimensional calculation model for the blanket design and optimization, not only will it consume extensive human and computer resources, but also make the computational process extremely complicated and lengthy. Considering that the radial arrangement of the functional zones, which has the greatest influence on the performance, is the basis of the detailed and accurate 3D design of the blanket, NTCOC, a N eutronics/ T hermal-hydraulics C oupling O ptimization C ode, which adopts simplified 1D Neutronics and 2D thermal-hydraulic calculation models, is developed for accelerating the radial build design and optimization of the blanket in this work. This code realizes the functions of both the automatic iterative updating the temperature-dependent cross-section libraries and the data transmission between the Neutronics and thermal-hydraulic calculation results through the inner and external coupling between the MCNP4C and CFD software, respectively. Therefore, this can make the comprehensive optimization analyses progress much faster and more accurate. In addition, a variable step length method is adopted to further improve the coupling optimization speed of this code, and several leading design objectives are set as the optimization criteria instead of taking all the possible practical engineering constrains into account. Finally, this code has been applied to optimize the radially arranged zones of a conceptual design scheme of Chinese Fusion Engineering Test Reactor (CFETR) helium cooled solid breeder blanket, which adopts mixed pebble beds as both the tritium breeder and neutron multiplier, under both the normal and critical conditions.
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evaluation and optimization of tritium breeding shielding and nuclear heating performances of the helium cooled solid breeder blanket for cfetr
International Journal of Hydrogen Energy, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Qiang Lian, Suizheng QiuAbstract:Abstract Chinese Fusion Engineering Test Reactor (CFETR) is a new test tokamak device being designed in China aimed to bridge gaps between ITER and DEMO. As one of the candidate tritium breeding blankets, a conceptual design scheme of the helium cooled solid breeder blanket has been proposed and a series of preliminary analyses have been carried out to access the performances. However, both the required global tritium breeding ratio for CFETR not less than 1.2 and its poor working conditions under intense radiation need further thorough Neutronics analyses and optimizations during the design phase. In this work, first, three-dimensional Neutronics model of CFETR was built, and the neutron wall loading and global TBR were obtained. The nuclear and thermal calculation results were automatically coupled, which could make the Neutronics calculation results more accurate and guaranteed they could always satisfy the corresponding thermal limits during the whole process. Then, the tritium breeding and shielding performances of both the outboard and inboard equatorial blanket modules were optimized for the comprehensive optimal schemes. The influences of Be/W armors on the shielding performance and TBR were also investigated. Finally, the nuclear heating rates and the neutron flux densities in different components were calculated based on the obtained comprehensive optimal scheme. In this paper, the Neutronics analyses and optimizations verified that the optimized conceptual design could well meet the tritium self-sufficiency and neutron shielding requirements, and this could provide a valuable reference for the further thermal-hydraulic analysis and structural optimization of the CFETR helium cooled solid breeder blanket.
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numerical research on the neutronic thermal hydraulic mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for cfetr
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Dalin Zhang, Jie Cheng, Wenxi TianAbstract:Abstract As one of the candidate tritium breeding blankets for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of the helium cooled solid breeder blanket has recently been proposed. The neutronic, thermal-hydraulic and mechanical characteristics of the blanket directly affect its tritium breeding and safety performance. Therefore, neutronic/thermal-hydraulic/mechanical coupling analyses are of vital importance for a reliable blanket design. In this work, first, three-dimensional Neutronics analysis and optimization of the typical outboard equatorial blanket module (No. 12) were performed for the comprehensive optimal scheme. Then, thermal and fluid dynamic analyses of the scheme under both normal and critical conditions were performed and coupled with the previous neutronic calculation results. With thermal-hydraulic boundaries, thermo-mechanical analyses of the structure materials under normal, critical and blanket over-pressurization conditions were carried out. In addition, several parametric sensitivity studies were also conducted to investigate the influences of the main parameters on the blanket temperature distributions. In this paper, the coupled analyses verify the reasonability of the optimized conceptual design preliminarily and can provide an important reference for the further analysis and optimization design of the CFETR helium cooled solid breeder blanket.
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steady and transient solutions of Neutronics problems based on finite volume method fvm with a cfd code
Progress in Nuclear Energy, 2015Co-Authors: Dalin Zhang, Wenxi Tian, Kunpeng Wang, Suizheng QiuAbstract:Abstract In recent years, Computational Fluid Dynamics (CFD) methodology has been widely used for solving multi-dimensional thermal-hydraulics problems in nuclear science and engineering. As for the Neutronics analysis, it mostly depends on the deterministic or probabilistic method codes which are independent of the thermal-hydraulic ones. Usually an extra interface program needs to be developed for the data exchange between the two kinds of codes in the coupled calculation. In this paper, a Temporal And Spatial Neutronics Analysis Module (TASNAM) in commercial CFD package FLUENT was developed based on the User Defined Function (UDF) and User Define Scalar (UDS) to solve the Neutronics problems. Neutron diffusion equations and delayed neutron precursors balance equations are discretized by finite volume method (FVM) and can be solved with CFD conservation equations simultaneously. In order to demonstrate the feasibility and accuracy of TASNAM in FLUENT, three Neutronics benchmark problems, the 2D-IAEA, 2D-TWIGL, and 2D-LRA benchmark problem are analyzed. The calculation results in the present paper have a good agreement with the reference values, which demonstrates that the TASNAM in FLUENT can solve Neutronics problems accurately.
Dalin Zhang - One of the best experts on this subject based on the ideXlab platform.
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development and application of a Neutronics thermal hydraulics coupling optimization code for the cfetr helium cooled solid breeder blanket with mixed pebble beds
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Suizheng QiuAbstract:Abstract As one of the most important components of fusion reactor, breeding blanket mainly accounts for tritium self-sufficiency, shielding and fusion energy collection. The performance of the blanket is mainly determined by the internal structural arrangement and material composition. However, if we directly adopt a three-dimensional calculation model for the blanket design and optimization, not only will it consume extensive human and computer resources, but also make the computational process extremely complicated and lengthy. Considering that the radial arrangement of the functional zones, which has the greatest influence on the performance, is the basis of the detailed and accurate 3D design of the blanket, NTCOC, a N eutronics/ T hermal-hydraulics C oupling O ptimization C ode, which adopts simplified 1D Neutronics and 2D thermal-hydraulic calculation models, is developed for accelerating the radial build design and optimization of the blanket in this work. This code realizes the functions of both the automatic iterative updating the temperature-dependent cross-section libraries and the data transmission between the Neutronics and thermal-hydraulic calculation results through the inner and external coupling between the MCNP4C and CFD software, respectively. Therefore, this can make the comprehensive optimization analyses progress much faster and more accurate. In addition, a variable step length method is adopted to further improve the coupling optimization speed of this code, and several leading design objectives are set as the optimization criteria instead of taking all the possible practical engineering constrains into account. Finally, this code has been applied to optimize the radially arranged zones of a conceptual design scheme of Chinese Fusion Engineering Test Reactor (CFETR) helium cooled solid breeder blanket, which adopts mixed pebble beds as both the tritium breeder and neutron multiplier, under both the normal and critical conditions.
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evaluation and optimization of tritium breeding shielding and nuclear heating performances of the helium cooled solid breeder blanket for cfetr
International Journal of Hydrogen Energy, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Qiang Lian, Suizheng QiuAbstract:Abstract Chinese Fusion Engineering Test Reactor (CFETR) is a new test tokamak device being designed in China aimed to bridge gaps between ITER and DEMO. As one of the candidate tritium breeding blankets, a conceptual design scheme of the helium cooled solid breeder blanket has been proposed and a series of preliminary analyses have been carried out to access the performances. However, both the required global tritium breeding ratio for CFETR not less than 1.2 and its poor working conditions under intense radiation need further thorough Neutronics analyses and optimizations during the design phase. In this work, first, three-dimensional Neutronics model of CFETR was built, and the neutron wall loading and global TBR were obtained. The nuclear and thermal calculation results were automatically coupled, which could make the Neutronics calculation results more accurate and guaranteed they could always satisfy the corresponding thermal limits during the whole process. Then, the tritium breeding and shielding performances of both the outboard and inboard equatorial blanket modules were optimized for the comprehensive optimal schemes. The influences of Be/W armors on the shielding performance and TBR were also investigated. Finally, the nuclear heating rates and the neutron flux densities in different components were calculated based on the obtained comprehensive optimal scheme. In this paper, the Neutronics analyses and optimizations verified that the optimized conceptual design could well meet the tritium self-sufficiency and neutron shielding requirements, and this could provide a valuable reference for the further thermal-hydraulic analysis and structural optimization of the CFETR helium cooled solid breeder blanket.
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numerical research on the neutronic thermal hydraulic mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for cfetr
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Dalin Zhang, Jie Cheng, Wenxi TianAbstract:Abstract As one of the candidate tritium breeding blankets for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of the helium cooled solid breeder blanket has recently been proposed. The neutronic, thermal-hydraulic and mechanical characteristics of the blanket directly affect its tritium breeding and safety performance. Therefore, neutronic/thermal-hydraulic/mechanical coupling analyses are of vital importance for a reliable blanket design. In this work, first, three-dimensional Neutronics analysis and optimization of the typical outboard equatorial blanket module (No. 12) were performed for the comprehensive optimal scheme. Then, thermal and fluid dynamic analyses of the scheme under both normal and critical conditions were performed and coupled with the previous neutronic calculation results. With thermal-hydraulic boundaries, thermo-mechanical analyses of the structure materials under normal, critical and blanket over-pressurization conditions were carried out. In addition, several parametric sensitivity studies were also conducted to investigate the influences of the main parameters on the blanket temperature distributions. In this paper, the coupled analyses verify the reasonability of the optimized conceptual design preliminarily and can provide an important reference for the further analysis and optimization design of the CFETR helium cooled solid breeder blanket.
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steady and transient solutions of Neutronics problems based on finite volume method fvm with a cfd code
Progress in Nuclear Energy, 2015Co-Authors: Dalin Zhang, Wenxi Tian, Kunpeng Wang, Suizheng QiuAbstract:Abstract In recent years, Computational Fluid Dynamics (CFD) methodology has been widely used for solving multi-dimensional thermal-hydraulics problems in nuclear science and engineering. As for the Neutronics analysis, it mostly depends on the deterministic or probabilistic method codes which are independent of the thermal-hydraulic ones. Usually an extra interface program needs to be developed for the data exchange between the two kinds of codes in the coupled calculation. In this paper, a Temporal And Spatial Neutronics Analysis Module (TASNAM) in commercial CFD package FLUENT was developed based on the User Defined Function (UDF) and User Define Scalar (UDS) to solve the Neutronics problems. Neutron diffusion equations and delayed neutron precursors balance equations are discretized by finite volume method (FVM) and can be solved with CFD conservation equations simultaneously. In order to demonstrate the feasibility and accuracy of TASNAM in FLUENT, three Neutronics benchmark problems, the 2D-IAEA, 2D-TWIGL, and 2D-LRA benchmark problem are analyzed. The calculation results in the present paper have a good agreement with the reference values, which demonstrates that the TASNAM in FLUENT can solve Neutronics problems accurately.
Jie Cheng - One of the best experts on this subject based on the ideXlab platform.
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development and application of a Neutronics thermal hydraulics coupling optimization code for the cfetr helium cooled solid breeder blanket with mixed pebble beds
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Suizheng QiuAbstract:Abstract As one of the most important components of fusion reactor, breeding blanket mainly accounts for tritium self-sufficiency, shielding and fusion energy collection. The performance of the blanket is mainly determined by the internal structural arrangement and material composition. However, if we directly adopt a three-dimensional calculation model for the blanket design and optimization, not only will it consume extensive human and computer resources, but also make the computational process extremely complicated and lengthy. Considering that the radial arrangement of the functional zones, which has the greatest influence on the performance, is the basis of the detailed and accurate 3D design of the blanket, NTCOC, a N eutronics/ T hermal-hydraulics C oupling O ptimization C ode, which adopts simplified 1D Neutronics and 2D thermal-hydraulic calculation models, is developed for accelerating the radial build design and optimization of the blanket in this work. This code realizes the functions of both the automatic iterative updating the temperature-dependent cross-section libraries and the data transmission between the Neutronics and thermal-hydraulic calculation results through the inner and external coupling between the MCNP4C and CFD software, respectively. Therefore, this can make the comprehensive optimization analyses progress much faster and more accurate. In addition, a variable step length method is adopted to further improve the coupling optimization speed of this code, and several leading design objectives are set as the optimization criteria instead of taking all the possible practical engineering constrains into account. Finally, this code has been applied to optimize the radially arranged zones of a conceptual design scheme of Chinese Fusion Engineering Test Reactor (CFETR) helium cooled solid breeder blanket, which adopts mixed pebble beds as both the tritium breeder and neutron multiplier, under both the normal and critical conditions.
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evaluation and optimization of tritium breeding shielding and nuclear heating performances of the helium cooled solid breeder blanket for cfetr
International Journal of Hydrogen Energy, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Qiang Lian, Suizheng QiuAbstract:Abstract Chinese Fusion Engineering Test Reactor (CFETR) is a new test tokamak device being designed in China aimed to bridge gaps between ITER and DEMO. As one of the candidate tritium breeding blankets, a conceptual design scheme of the helium cooled solid breeder blanket has been proposed and a series of preliminary analyses have been carried out to access the performances. However, both the required global tritium breeding ratio for CFETR not less than 1.2 and its poor working conditions under intense radiation need further thorough Neutronics analyses and optimizations during the design phase. In this work, first, three-dimensional Neutronics model of CFETR was built, and the neutron wall loading and global TBR were obtained. The nuclear and thermal calculation results were automatically coupled, which could make the Neutronics calculation results more accurate and guaranteed they could always satisfy the corresponding thermal limits during the whole process. Then, the tritium breeding and shielding performances of both the outboard and inboard equatorial blanket modules were optimized for the comprehensive optimal schemes. The influences of Be/W armors on the shielding performance and TBR were also investigated. Finally, the nuclear heating rates and the neutron flux densities in different components were calculated based on the obtained comprehensive optimal scheme. In this paper, the Neutronics analyses and optimizations verified that the optimized conceptual design could well meet the tritium self-sufficiency and neutron shielding requirements, and this could provide a valuable reference for the further thermal-hydraulic analysis and structural optimization of the CFETR helium cooled solid breeder blanket.
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numerical research on the neutronic thermal hydraulic mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for cfetr
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Dalin Zhang, Jie Cheng, Wenxi TianAbstract:Abstract As one of the candidate tritium breeding blankets for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of the helium cooled solid breeder blanket has recently been proposed. The neutronic, thermal-hydraulic and mechanical characteristics of the blanket directly affect its tritium breeding and safety performance. Therefore, neutronic/thermal-hydraulic/mechanical coupling analyses are of vital importance for a reliable blanket design. In this work, first, three-dimensional Neutronics analysis and optimization of the typical outboard equatorial blanket module (No. 12) were performed for the comprehensive optimal scheme. Then, thermal and fluid dynamic analyses of the scheme under both normal and critical conditions were performed and coupled with the previous neutronic calculation results. With thermal-hydraulic boundaries, thermo-mechanical analyses of the structure materials under normal, critical and blanket over-pressurization conditions were carried out. In addition, several parametric sensitivity studies were also conducted to investigate the influences of the main parameters on the blanket temperature distributions. In this paper, the coupled analyses verify the reasonability of the optimized conceptual design preliminarily and can provide an important reference for the further analysis and optimization design of the CFETR helium cooled solid breeder blanket.
Shijie Cui - One of the best experts on this subject based on the ideXlab platform.
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development and application of a Neutronics thermal hydraulics coupling optimization code for the cfetr helium cooled solid breeder blanket with mixed pebble beds
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Suizheng QiuAbstract:Abstract As one of the most important components of fusion reactor, breeding blanket mainly accounts for tritium self-sufficiency, shielding and fusion energy collection. The performance of the blanket is mainly determined by the internal structural arrangement and material composition. However, if we directly adopt a three-dimensional calculation model for the blanket design and optimization, not only will it consume extensive human and computer resources, but also make the computational process extremely complicated and lengthy. Considering that the radial arrangement of the functional zones, which has the greatest influence on the performance, is the basis of the detailed and accurate 3D design of the blanket, NTCOC, a N eutronics/ T hermal-hydraulics C oupling O ptimization C ode, which adopts simplified 1D Neutronics and 2D thermal-hydraulic calculation models, is developed for accelerating the radial build design and optimization of the blanket in this work. This code realizes the functions of both the automatic iterative updating the temperature-dependent cross-section libraries and the data transmission between the Neutronics and thermal-hydraulic calculation results through the inner and external coupling between the MCNP4C and CFD software, respectively. Therefore, this can make the comprehensive optimization analyses progress much faster and more accurate. In addition, a variable step length method is adopted to further improve the coupling optimization speed of this code, and several leading design objectives are set as the optimization criteria instead of taking all the possible practical engineering constrains into account. Finally, this code has been applied to optimize the radially arranged zones of a conceptual design scheme of Chinese Fusion Engineering Test Reactor (CFETR) helium cooled solid breeder blanket, which adopts mixed pebble beds as both the tritium breeder and neutron multiplier, under both the normal and critical conditions.
-
evaluation and optimization of tritium breeding shielding and nuclear heating performances of the helium cooled solid breeder blanket for cfetr
International Journal of Hydrogen Energy, 2017Co-Authors: Shijie Cui, Wenxi Tian, Dalin Zhang, Jie Cheng, Qiang Lian, Suizheng QiuAbstract:Abstract Chinese Fusion Engineering Test Reactor (CFETR) is a new test tokamak device being designed in China aimed to bridge gaps between ITER and DEMO. As one of the candidate tritium breeding blankets, a conceptual design scheme of the helium cooled solid breeder blanket has been proposed and a series of preliminary analyses have been carried out to access the performances. However, both the required global tritium breeding ratio for CFETR not less than 1.2 and its poor working conditions under intense radiation need further thorough Neutronics analyses and optimizations during the design phase. In this work, first, three-dimensional Neutronics model of CFETR was built, and the neutron wall loading and global TBR were obtained. The nuclear and thermal calculation results were automatically coupled, which could make the Neutronics calculation results more accurate and guaranteed they could always satisfy the corresponding thermal limits during the whole process. Then, the tritium breeding and shielding performances of both the outboard and inboard equatorial blanket modules were optimized for the comprehensive optimal schemes. The influences of Be/W armors on the shielding performance and TBR were also investigated. Finally, the nuclear heating rates and the neutron flux densities in different components were calculated based on the obtained comprehensive optimal scheme. In this paper, the Neutronics analyses and optimizations verified that the optimized conceptual design could well meet the tritium self-sufficiency and neutron shielding requirements, and this could provide a valuable reference for the further thermal-hydraulic analysis and structural optimization of the CFETR helium cooled solid breeder blanket.
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numerical research on the neutronic thermal hydraulic mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for cfetr
Fusion Engineering and Design, 2017Co-Authors: Shijie Cui, Dalin Zhang, Jie Cheng, Wenxi TianAbstract:Abstract As one of the candidate tritium breeding blankets for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of the helium cooled solid breeder blanket has recently been proposed. The neutronic, thermal-hydraulic and mechanical characteristics of the blanket directly affect its tritium breeding and safety performance. Therefore, neutronic/thermal-hydraulic/mechanical coupling analyses are of vital importance for a reliable blanket design. In this work, first, three-dimensional Neutronics analysis and optimization of the typical outboard equatorial blanket module (No. 12) were performed for the comprehensive optimal scheme. Then, thermal and fluid dynamic analyses of the scheme under both normal and critical conditions were performed and coupled with the previous neutronic calculation results. With thermal-hydraulic boundaries, thermo-mechanical analyses of the structure materials under normal, critical and blanket over-pressurization conditions were carried out. In addition, several parametric sensitivity studies were also conducted to investigate the influences of the main parameters on the blanket temperature distributions. In this paper, the coupled analyses verify the reasonability of the optimized conceptual design preliminarily and can provide an important reference for the further analysis and optimization design of the CFETR helium cooled solid breeder blanket.