The Experts below are selected from a list of 2439 Experts worldwide ranked by ideXlab platform
Pallippattu Krishnan Vijayan - One of the best experts on this subject based on the ideXlab platform.
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Reactor Physics and Thermal Hydraulic Analysis of Annular Fuel Rod Cluster for Advanced Heavy Water Reactor
Energy Procedia, 2015Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract Internally and externally cooled annular fuel Rod is an advantage over solid fuel Rod in reactor core design in order to improve core power density and safety aspects like Minimum Critical Heat Flux Ratio (MCHFR) and lower centerline temperature. Various Cluster geometries with annular fuel Rod have been suggested for Advanced Heavy Water Reactor (AHWR) depending upon the operating parameters. We had already presented the design of 33 Rod annular fuel Cluster for AHWR in previous paper. The 33 pin fuel Cluster had a lower MCHFR and the reactor power could be increased by about 20% only. The fuel bundle geometry presented in this paper is an improvised to obtain larger MCHFR and better physics performance. The AHWR uses a fuel Cluster of 54 solid fuel Rods and is designed for 920MWth. We have designed an annual fuel Cluster with 19 fuel Rods which meets all the thermal design margin as well as gives 30% more power than the solid fuel Rod Cluster without any considerable changes in design basis. Reactor core power calculations are carried out and then optimized burn up is obtained. This research article mainly deals with the improvements made in the annular fuel Rod bundle to get optimized burn up and core power distribution.
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design and analysis of 19 pin annular fuel Rod Cluster for pressure tube type boiling water reactor
Nuclear Engineering and Design, 2014Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Arnab Dasgupta, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract An assessment of 33 pin annular fuel Rod Cluster has been carried out previously for possible use in a pressure tube type boiling water reactor. Despite the benefits such as negative coolant void reactivity and larger heat transfer area, the 33 pin annular fuel Rod Cluster is having lower discharge burn up as compared to solid fuel Rod Cluster when all other parameters are kept the same. The power rating of this design cannot be increased beyond 20% of the corresponding solid fuel Rod Cluster. The limitation on the power is not due to physics parameters rather it comes from the thermal hydraulics side. In order to increase power rating of the annular fuel Cluster, keeping same pressure tube diameter, the pin diameter was increased, achieving larger inside flow area. However, this reduces the number of annular fuel Rods. In spite of this, the power of the annular fuel Cluster can be increased by 30% compared to the solid fuel Rod Cluster. This makes the nineteen pin annular fuel Rod Cluster a suitable option to extract more power without any major changes in the existing design of the fuel. In the present study reactor physics and thermal hydraulic analysis carried out with different annular fuel Rod Cluster geometry is reported in detail.
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design of 33 pin annular fuel Rod Cluster for advanced heavy water reactor
Nuclear Engineering and Design, 2013Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan Vijayan, S. GanesanAbstract:Abstract The Advanced Heavy Water Reactor (AHWR) is a vertical pressure tube type reactor designed for utilizing thorium fuel with boiling light water as coolant and heavy water as moderator. The AHWR has several passive features, the major ones being heat removal through natural circulation, decay heat removal through passive means by the way of isolation condensers and a large heat sink in the form of gravity driven water pool. In the existing design of AHWR, the fuel Rod Cluster has solid fuel pins. The limitation on it is the Minimum Critical Heat Flux Ratio (MCHFR), which comes from coolant characteristics. In order to improve power output from the AHWR we are trying to design internally and externally cooled annular fuel Rod Cluster for AHWR. The fuel Cluster design would have to be qualified from physics and thermal hydraulic behavior. In order to satisfy the design objectives, a detailed thermal hydraulics and physics simulation has been done.
A P Deokule - One of the best experts on this subject based on the ideXlab platform.
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Reactor Physics and Thermal Hydraulic Analysis of Annular Fuel Rod Cluster for Advanced Heavy Water Reactor
Energy Procedia, 2015Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract Internally and externally cooled annular fuel Rod is an advantage over solid fuel Rod in reactor core design in order to improve core power density and safety aspects like Minimum Critical Heat Flux Ratio (MCHFR) and lower centerline temperature. Various Cluster geometries with annular fuel Rod have been suggested for Advanced Heavy Water Reactor (AHWR) depending upon the operating parameters. We had already presented the design of 33 Rod annular fuel Cluster for AHWR in previous paper. The 33 pin fuel Cluster had a lower MCHFR and the reactor power could be increased by about 20% only. The fuel bundle geometry presented in this paper is an improvised to obtain larger MCHFR and better physics performance. The AHWR uses a fuel Cluster of 54 solid fuel Rods and is designed for 920MWth. We have designed an annual fuel Cluster with 19 fuel Rods which meets all the thermal design margin as well as gives 30% more power than the solid fuel Rod Cluster without any considerable changes in design basis. Reactor core power calculations are carried out and then optimized burn up is obtained. This research article mainly deals with the improvements made in the annular fuel Rod bundle to get optimized burn up and core power distribution.
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design and analysis of 19 pin annular fuel Rod Cluster for pressure tube type boiling water reactor
Nuclear Engineering and Design, 2014Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Arnab Dasgupta, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract An assessment of 33 pin annular fuel Rod Cluster has been carried out previously for possible use in a pressure tube type boiling water reactor. Despite the benefits such as negative coolant void reactivity and larger heat transfer area, the 33 pin annular fuel Rod Cluster is having lower discharge burn up as compared to solid fuel Rod Cluster when all other parameters are kept the same. The power rating of this design cannot be increased beyond 20% of the corresponding solid fuel Rod Cluster. The limitation on the power is not due to physics parameters rather it comes from the thermal hydraulics side. In order to increase power rating of the annular fuel Cluster, keeping same pressure tube diameter, the pin diameter was increased, achieving larger inside flow area. However, this reduces the number of annular fuel Rods. In spite of this, the power of the annular fuel Cluster can be increased by 30% compared to the solid fuel Rod Cluster. This makes the nineteen pin annular fuel Rod Cluster a suitable option to extract more power without any major changes in the existing design of the fuel. In the present study reactor physics and thermal hydraulic analysis carried out with different annular fuel Rod Cluster geometry is reported in detail.
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design of 33 pin annular fuel Rod Cluster for advanced heavy water reactor
Nuclear Engineering and Design, 2013Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan Vijayan, S. GanesanAbstract:Abstract The Advanced Heavy Water Reactor (AHWR) is a vertical pressure tube type reactor designed for utilizing thorium fuel with boiling light water as coolant and heavy water as moderator. The AHWR has several passive features, the major ones being heat removal through natural circulation, decay heat removal through passive means by the way of isolation condensers and a large heat sink in the form of gravity driven water pool. In the existing design of AHWR, the fuel Rod Cluster has solid fuel pins. The limitation on it is the Minimum Critical Heat Flux Ratio (MCHFR), which comes from coolant characteristics. In order to improve power output from the AHWR we are trying to design internally and externally cooled annular fuel Rod Cluster for AHWR. The fuel Cluster design would have to be qualified from physics and thermal hydraulic behavior. In order to satisfy the design objectives, a detailed thermal hydraulics and physics simulation has been done.
Kannan Umasankari - One of the best experts on this subject based on the ideXlab platform.
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Reactor Physics and Thermal Hydraulic Analysis of Annular Fuel Rod Cluster for Advanced Heavy Water Reactor
Energy Procedia, 2015Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract Internally and externally cooled annular fuel Rod is an advantage over solid fuel Rod in reactor core design in order to improve core power density and safety aspects like Minimum Critical Heat Flux Ratio (MCHFR) and lower centerline temperature. Various Cluster geometries with annular fuel Rod have been suggested for Advanced Heavy Water Reactor (AHWR) depending upon the operating parameters. We had already presented the design of 33 Rod annular fuel Cluster for AHWR in previous paper. The 33 pin fuel Cluster had a lower MCHFR and the reactor power could be increased by about 20% only. The fuel bundle geometry presented in this paper is an improvised to obtain larger MCHFR and better physics performance. The AHWR uses a fuel Cluster of 54 solid fuel Rods and is designed for 920MWth. We have designed an annual fuel Cluster with 19 fuel Rods which meets all the thermal design margin as well as gives 30% more power than the solid fuel Rod Cluster without any considerable changes in design basis. Reactor core power calculations are carried out and then optimized burn up is obtained. This research article mainly deals with the improvements made in the annular fuel Rod bundle to get optimized burn up and core power distribution.
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design and analysis of 19 pin annular fuel Rod Cluster for pressure tube type boiling water reactor
Nuclear Engineering and Design, 2014Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Arnab Dasgupta, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract An assessment of 33 pin annular fuel Rod Cluster has been carried out previously for possible use in a pressure tube type boiling water reactor. Despite the benefits such as negative coolant void reactivity and larger heat transfer area, the 33 pin annular fuel Rod Cluster is having lower discharge burn up as compared to solid fuel Rod Cluster when all other parameters are kept the same. The power rating of this design cannot be increased beyond 20% of the corresponding solid fuel Rod Cluster. The limitation on the power is not due to physics parameters rather it comes from the thermal hydraulics side. In order to increase power rating of the annular fuel Cluster, keeping same pressure tube diameter, the pin diameter was increased, achieving larger inside flow area. However, this reduces the number of annular fuel Rods. In spite of this, the power of the annular fuel Cluster can be increased by 30% compared to the solid fuel Rod Cluster. This makes the nineteen pin annular fuel Rod Cluster a suitable option to extract more power without any major changes in the existing design of the fuel. In the present study reactor physics and thermal hydraulic analysis carried out with different annular fuel Rod Cluster geometry is reported in detail.
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design of 33 pin annular fuel Rod Cluster for advanced heavy water reactor
Nuclear Engineering and Design, 2013Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan Vijayan, S. GanesanAbstract:Abstract The Advanced Heavy Water Reactor (AHWR) is a vertical pressure tube type reactor designed for utilizing thorium fuel with boiling light water as coolant and heavy water as moderator. The AHWR has several passive features, the major ones being heat removal through natural circulation, decay heat removal through passive means by the way of isolation condensers and a large heat sink in the form of gravity driven water pool. In the existing design of AHWR, the fuel Rod Cluster has solid fuel pins. The limitation on it is the Minimum Critical Heat Flux Ratio (MCHFR), which comes from coolant characteristics. In order to improve power output from the AHWR we are trying to design internally and externally cooled annular fuel Rod Cluster for AHWR. The fuel Cluster design would have to be qualified from physics and thermal hydraulic behavior. In order to satisfy the design objectives, a detailed thermal hydraulics and physics simulation has been done.
D K Chandraker - One of the best experts on this subject based on the ideXlab platform.
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Reactor Physics and Thermal Hydraulic Analysis of Annular Fuel Rod Cluster for Advanced Heavy Water Reactor
Energy Procedia, 2015Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract Internally and externally cooled annular fuel Rod is an advantage over solid fuel Rod in reactor core design in order to improve core power density and safety aspects like Minimum Critical Heat Flux Ratio (MCHFR) and lower centerline temperature. Various Cluster geometries with annular fuel Rod have been suggested for Advanced Heavy Water Reactor (AHWR) depending upon the operating parameters. We had already presented the design of 33 Rod annular fuel Cluster for AHWR in previous paper. The 33 pin fuel Cluster had a lower MCHFR and the reactor power could be increased by about 20% only. The fuel bundle geometry presented in this paper is an improvised to obtain larger MCHFR and better physics performance. The AHWR uses a fuel Cluster of 54 solid fuel Rods and is designed for 920MWth. We have designed an annual fuel Cluster with 19 fuel Rods which meets all the thermal design margin as well as gives 30% more power than the solid fuel Rod Cluster without any considerable changes in design basis. Reactor core power calculations are carried out and then optimized burn up is obtained. This research article mainly deals with the improvements made in the annular fuel Rod bundle to get optimized burn up and core power distribution.
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design and analysis of 19 pin annular fuel Rod Cluster for pressure tube type boiling water reactor
Nuclear Engineering and Design, 2014Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Arnab Dasgupta, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract An assessment of 33 pin annular fuel Rod Cluster has been carried out previously for possible use in a pressure tube type boiling water reactor. Despite the benefits such as negative coolant void reactivity and larger heat transfer area, the 33 pin annular fuel Rod Cluster is having lower discharge burn up as compared to solid fuel Rod Cluster when all other parameters are kept the same. The power rating of this design cannot be increased beyond 20% of the corresponding solid fuel Rod Cluster. The limitation on the power is not due to physics parameters rather it comes from the thermal hydraulics side. In order to increase power rating of the annular fuel Cluster, keeping same pressure tube diameter, the pin diameter was increased, achieving larger inside flow area. However, this reduces the number of annular fuel Rods. In spite of this, the power of the annular fuel Cluster can be increased by 30% compared to the solid fuel Rod Cluster. This makes the nineteen pin annular fuel Rod Cluster a suitable option to extract more power without any major changes in the existing design of the fuel. In the present study reactor physics and thermal hydraulic analysis carried out with different annular fuel Rod Cluster geometry is reported in detail.
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design of 33 pin annular fuel Rod Cluster for advanced heavy water reactor
Nuclear Engineering and Design, 2013Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan Vijayan, S. GanesanAbstract:Abstract The Advanced Heavy Water Reactor (AHWR) is a vertical pressure tube type reactor designed for utilizing thorium fuel with boiling light water as coolant and heavy water as moderator. The AHWR has several passive features, the major ones being heat removal through natural circulation, decay heat removal through passive means by the way of isolation condensers and a large heat sink in the form of gravity driven water pool. In the existing design of AHWR, the fuel Rod Cluster has solid fuel pins. The limitation on it is the Minimum Critical Heat Flux Ratio (MCHFR), which comes from coolant characteristics. In order to improve power output from the AHWR we are trying to design internally and externally cooled annular fuel Rod Cluster for AHWR. The fuel Cluster design would have to be qualified from physics and thermal hydraulic behavior. In order to satisfy the design objectives, a detailed thermal hydraulics and physics simulation has been done.
A K Vishnoi - One of the best experts on this subject based on the ideXlab platform.
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Reactor Physics and Thermal Hydraulic Analysis of Annular Fuel Rod Cluster for Advanced Heavy Water Reactor
Energy Procedia, 2015Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract Internally and externally cooled annular fuel Rod is an advantage over solid fuel Rod in reactor core design in order to improve core power density and safety aspects like Minimum Critical Heat Flux Ratio (MCHFR) and lower centerline temperature. Various Cluster geometries with annular fuel Rod have been suggested for Advanced Heavy Water Reactor (AHWR) depending upon the operating parameters. We had already presented the design of 33 Rod annular fuel Cluster for AHWR in previous paper. The 33 pin fuel Cluster had a lower MCHFR and the reactor power could be increased by about 20% only. The fuel bundle geometry presented in this paper is an improvised to obtain larger MCHFR and better physics performance. The AHWR uses a fuel Cluster of 54 solid fuel Rods and is designed for 920MWth. We have designed an annual fuel Cluster with 19 fuel Rods which meets all the thermal design margin as well as gives 30% more power than the solid fuel Rod Cluster without any considerable changes in design basis. Reactor core power calculations are carried out and then optimized burn up is obtained. This research article mainly deals with the improvements made in the annular fuel Rod bundle to get optimized burn up and core power distribution.
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design and analysis of 19 pin annular fuel Rod Cluster for pressure tube type boiling water reactor
Nuclear Engineering and Design, 2014Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Arnab Dasgupta, Kannan Umasankari, Pallippattu Krishnan VijayanAbstract:Abstract An assessment of 33 pin annular fuel Rod Cluster has been carried out previously for possible use in a pressure tube type boiling water reactor. Despite the benefits such as negative coolant void reactivity and larger heat transfer area, the 33 pin annular fuel Rod Cluster is having lower discharge burn up as compared to solid fuel Rod Cluster when all other parameters are kept the same. The power rating of this design cannot be increased beyond 20% of the corresponding solid fuel Rod Cluster. The limitation on the power is not due to physics parameters rather it comes from the thermal hydraulics side. In order to increase power rating of the annular fuel Cluster, keeping same pressure tube diameter, the pin diameter was increased, achieving larger inside flow area. However, this reduces the number of annular fuel Rods. In spite of this, the power of the annular fuel Cluster can be increased by 30% compared to the solid fuel Rod Cluster. This makes the nineteen pin annular fuel Rod Cluster a suitable option to extract more power without any major changes in the existing design of the fuel. In the present study reactor physics and thermal hydraulic analysis carried out with different annular fuel Rod Cluster geometry is reported in detail.
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design of 33 pin annular fuel Rod Cluster for advanced heavy water reactor
Nuclear Engineering and Design, 2013Co-Authors: A P Deokule, A K Vishnoi, D K Chandraker, Kannan Umasankari, Pallippattu Krishnan Vijayan, S. GanesanAbstract:Abstract The Advanced Heavy Water Reactor (AHWR) is a vertical pressure tube type reactor designed for utilizing thorium fuel with boiling light water as coolant and heavy water as moderator. The AHWR has several passive features, the major ones being heat removal through natural circulation, decay heat removal through passive means by the way of isolation condensers and a large heat sink in the form of gravity driven water pool. In the existing design of AHWR, the fuel Rod Cluster has solid fuel pins. The limitation on it is the Minimum Critical Heat Flux Ratio (MCHFR), which comes from coolant characteristics. In order to improve power output from the AHWR we are trying to design internally and externally cooled annular fuel Rod Cluster for AHWR. The fuel Cluster design would have to be qualified from physics and thermal hydraulic behavior. In order to satisfy the design objectives, a detailed thermal hydraulics and physics simulation has been done.
