The Experts below are selected from a list of 2475 Experts worldwide ranked by ideXlab platform
James J Sienicki - One of the best experts on this subject based on the ideXlab platform.
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transient accident analysis of a supercritical carbon dioxide Brayton Cycle energy converter coupled to an autonomous lead cooled fast reactor
Nuclear Engineering and Design, 2008Co-Authors: Anton Moisseytsev, James J SienickiAbstract:Abstract The supercritical carbon dioxide (S-CO2) Brayton Cycle is a promising advanced alternative to the Rankine steam Cycle and recuperated Gas Brayton Cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO2 Brayton Cycle coupled to an autonomous, natural circulation lead-cooled fast reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios.
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transient accident analysis of a supercritical carbon dioxide Brayton Cycle energy converter coupled to an autonomous lead cooled fast reactor
Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 2006Co-Authors: Anton Moisseytsev, James J SienickiAbstract:The Supercritical Carbon Dioxide (S-CO2 ) Brayton Cycle is a promising advanced alternative to the Rankine saturated steam Cycle and recuperated Gas Brayton Cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO2 Brayton Cycle coupled to an autonomous, natural circulation Lead-Cooled Fast Reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios.Copyright © 2006 by ASME
Anton Moisseytsev - One of the best experts on this subject based on the ideXlab platform.
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transient accident analysis of a supercritical carbon dioxide Brayton Cycle energy converter coupled to an autonomous lead cooled fast reactor
Nuclear Engineering and Design, 2008Co-Authors: Anton Moisseytsev, James J SienickiAbstract:Abstract The supercritical carbon dioxide (S-CO2) Brayton Cycle is a promising advanced alternative to the Rankine steam Cycle and recuperated Gas Brayton Cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO2 Brayton Cycle coupled to an autonomous, natural circulation lead-cooled fast reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios.
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transient accident analysis of a supercritical carbon dioxide Brayton Cycle energy converter coupled to an autonomous lead cooled fast reactor
Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 2006Co-Authors: Anton Moisseytsev, James J SienickiAbstract:The Supercritical Carbon Dioxide (S-CO2 ) Brayton Cycle is a promising advanced alternative to the Rankine saturated steam Cycle and recuperated Gas Brayton Cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO2 Brayton Cycle coupled to an autonomous, natural circulation Lead-Cooled Fast Reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios.Copyright © 2006 by ASME
Moo Hwan Kim - One of the best experts on this subject based on the ideXlab platform.
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performance and size comparison of two stage and three stage axial turbines for a nitrogen Gas Brayton Cycle coupled with a sodium cooled fast reactor
Nuclear Engineering and Design, 2021Co-Authors: Jae Hyun Choi, Jung Yoon, Jaehyuk Eoh, Moo Hwan KimAbstract:Abstract A nitrogen (N2) Brayton Cycle is considered as an alternative to the conventional steam Rankine Cycle to overcome essential risk during pressure boundary rupture accidents with sodium-water reaction in a steam-generator of a sodium-cooled fast reactor (SFR). The objectives of this study are to estimate the turbine performances after proposing three-dimensional (3-D) blade designs and to suggest an option of detailed turbine design for N2 Brayton Cycle-SFR applications. A free-vortex design method was applied in the 3-D design. Three candidates, including two- and three-stage designs, were selected from the Smith charts. Aerodynamic losses were investigated and compared through computational fluid dynamics analyses for the cases selected above. According to the results, rotor blade with milder curvature increased proportions of secondary and tip leakage losses among the total aerodynamic loss. When comprehensively considering the turbomachinery size and Cycle thermal efficiency, the size of the two-stage turbine could be reduced to under 55% of the three-stage turbine size, resulting in no significant decrement of the Cycle efficiency.
Jae Hyun Choi - One of the best experts on this subject based on the ideXlab platform.
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performance and size comparison of two stage and three stage axial turbines for a nitrogen Gas Brayton Cycle coupled with a sodium cooled fast reactor
Nuclear Engineering and Design, 2021Co-Authors: Jae Hyun Choi, Jung Yoon, Jaehyuk Eoh, Moo Hwan KimAbstract:Abstract A nitrogen (N2) Brayton Cycle is considered as an alternative to the conventional steam Rankine Cycle to overcome essential risk during pressure boundary rupture accidents with sodium-water reaction in a steam-generator of a sodium-cooled fast reactor (SFR). The objectives of this study are to estimate the turbine performances after proposing three-dimensional (3-D) blade designs and to suggest an option of detailed turbine design for N2 Brayton Cycle-SFR applications. A free-vortex design method was applied in the 3-D design. Three candidates, including two- and three-stage designs, were selected from the Smith charts. Aerodynamic losses were investigated and compared through computational fluid dynamics analyses for the cases selected above. According to the results, rotor blade with milder curvature increased proportions of secondary and tip leakage losses among the total aerodynamic loss. When comprehensively considering the turbomachinery size and Cycle thermal efficiency, the size of the two-stage turbine could be reduced to under 55% of the three-stage turbine size, resulting in no significant decrement of the Cycle efficiency.
Jaehyuk Eoh - One of the best experts on this subject based on the ideXlab platform.
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performance and size comparison of two stage and three stage axial turbines for a nitrogen Gas Brayton Cycle coupled with a sodium cooled fast reactor
Nuclear Engineering and Design, 2021Co-Authors: Jae Hyun Choi, Jung Yoon, Jaehyuk Eoh, Moo Hwan KimAbstract:Abstract A nitrogen (N2) Brayton Cycle is considered as an alternative to the conventional steam Rankine Cycle to overcome essential risk during pressure boundary rupture accidents with sodium-water reaction in a steam-generator of a sodium-cooled fast reactor (SFR). The objectives of this study are to estimate the turbine performances after proposing three-dimensional (3-D) blade designs and to suggest an option of detailed turbine design for N2 Brayton Cycle-SFR applications. A free-vortex design method was applied in the 3-D design. Three candidates, including two- and three-stage designs, were selected from the Smith charts. Aerodynamic losses were investigated and compared through computational fluid dynamics analyses for the cases selected above. According to the results, rotor blade with milder curvature increased proportions of secondary and tip leakage losses among the total aerodynamic loss. When comprehensively considering the turbomachinery size and Cycle thermal efficiency, the size of the two-stage turbine could be reduced to under 55% of the three-stage turbine size, resulting in no significant decrement of the Cycle efficiency.
