The Experts below are selected from a list of 38811 Experts worldwide ranked by ideXlab platform
Yu Zou - One of the best experts on this subject based on the ideXlab platform.
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modeling and control of nuclear Reactor Cores for electricity generation a review of advanced technologies
Renewable & Sustainable Energy Reviews, 2016Co-Authors: Xueqian Wang, Bin Liang, Bo Zhang, Yu ZouAbstract:This investigation is to review advanced technologies for modeling and control of Reactor Cores in nuclear power plants for electricity generation. A Reactor Core in a nuclear power plant is the key part as the hot source with radioactivity nuclear fuel, which possesses security risks and economic potential. Incapacity of a nuclear power plant to carry out desired control of its Core can result in either higher operating costs or a reduction in system security and reliability, and the implementation of desirable control for the Core can improve security and effectiveness of the nuclear power plant. Generally speaking, the Reactor Core control contains the power (or coolant temperature) control and axial power difference (namely power distribution) control of the Core. The Core power control is to regulate the Core power, and the Core load following control is to regulate the Core power and axial power difference simultaneously. Modeling Reactor Cores is the inevitable preliminary work for research of Reactor Core control. Over the decades, continuous work has been devoted to the research of including modeling, power and load following control for Reactor Cores. In this paper, the review on advanced technologies for modeling, power and load following control of Reactor Cores is presented. Modeling approaches for Reactor Cores are reviewed such as the point Reactor Core modeling. Power control methods for Reactor Cores are reviewed such as the feedback control with a state observer. Load following control techniques for Reactor Cores are reviewed such as Mode A, Mode G, Mode T, Mechanical Shim and advanced control methods of containing multivariable frequency control, etc. The review in this paper can contribute to comprehend the past work with respective advantages, and then exploit novel research directions for development of nuclear power plants.
Bo Zhang - One of the best experts on this subject based on the ideXlab platform.
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modeling and control of nuclear Reactor Cores for electricity generation a review of advanced technologies
Renewable & Sustainable Energy Reviews, 2016Co-Authors: Xueqian Wang, Bin Liang, Bo Zhang, Yu ZouAbstract:This investigation is to review advanced technologies for modeling and control of Reactor Cores in nuclear power plants for electricity generation. A Reactor Core in a nuclear power plant is the key part as the hot source with radioactivity nuclear fuel, which possesses security risks and economic potential. Incapacity of a nuclear power plant to carry out desired control of its Core can result in either higher operating costs or a reduction in system security and reliability, and the implementation of desirable control for the Core can improve security and effectiveness of the nuclear power plant. Generally speaking, the Reactor Core control contains the power (or coolant temperature) control and axial power difference (namely power distribution) control of the Core. The Core power control is to regulate the Core power, and the Core load following control is to regulate the Core power and axial power difference simultaneously. Modeling Reactor Cores is the inevitable preliminary work for research of Reactor Core control. Over the decades, continuous work has been devoted to the research of including modeling, power and load following control for Reactor Cores. In this paper, the review on advanced technologies for modeling, power and load following control of Reactor Cores is presented. Modeling approaches for Reactor Cores are reviewed such as the point Reactor Core modeling. Power control methods for Reactor Cores are reviewed such as the feedback control with a state observer. Load following control techniques for Reactor Cores are reviewed such as Mode A, Mode G, Mode T, Mechanical Shim and advanced control methods of containing multivariable frequency control, etc. The review in this paper can contribute to comprehend the past work with respective advantages, and then exploit novel research directions for development of nuclear power plants.
Deokjung Lee - One of the best experts on this subject based on the ideXlab platform.
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On the diffusion coefficient calculation in two-step light water Reactor Core analysis
Journal of Nuclear Science and Technology, 2017Co-Authors: Sooyoung Choi, Kord Smith, Hanjoo Kim, Taewoo Tak, Deokjung LeeAbstract:ABSTRACTThis paper presents consistent and rigorous accuracy assessments of various methods for calculating the diffusion coefficients in a two-step Reactor Core analysis of light water Reactors (LWRs). The diffusion coefficients are significantly affected by the transport correction and critical spectrum calculations. There are various methods for the transport corrections (inflow/outflow/hybrid corrections) and critical spectrum calculations (B1/P1/CASMO-4E methods) so that it is necessary to decide the best combination to achieve a high accuracy in the transport/diffusion two-step analysis. Numerical tests are performed step-by-step to search for the best combination of the methods by comparing each other the transport one-step results, transport/diffusion two-step results, and Monte Carlo results. Numerical test results with a large and a small LWR Core show that the combination of inflow transport correction and CASMO-4E critical spectrum calculation is most accurate than the other combinations in te...
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cell homogenization method for pin by pin neutron transport calculations
Nuclear Science and Engineering, 2011Co-Authors: Tomasz Kozlowski, Thomas Downar, Deokjung LeeAbstract:AbstractFor practical Reactor Core applications, low-order transport approximations such as SP3 have been shown to provide sufficient accuracy for both static and transient calculations with consid...
Xueqian Wang - One of the best experts on this subject based on the ideXlab platform.
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modeling and control of nuclear Reactor Cores for electricity generation a review of advanced technologies
Renewable & Sustainable Energy Reviews, 2016Co-Authors: Xueqian Wang, Bin Liang, Bo Zhang, Yu ZouAbstract:This investigation is to review advanced technologies for modeling and control of Reactor Cores in nuclear power plants for electricity generation. A Reactor Core in a nuclear power plant is the key part as the hot source with radioactivity nuclear fuel, which possesses security risks and economic potential. Incapacity of a nuclear power plant to carry out desired control of its Core can result in either higher operating costs or a reduction in system security and reliability, and the implementation of desirable control for the Core can improve security and effectiveness of the nuclear power plant. Generally speaking, the Reactor Core control contains the power (or coolant temperature) control and axial power difference (namely power distribution) control of the Core. The Core power control is to regulate the Core power, and the Core load following control is to regulate the Core power and axial power difference simultaneously. Modeling Reactor Cores is the inevitable preliminary work for research of Reactor Core control. Over the decades, continuous work has been devoted to the research of including modeling, power and load following control for Reactor Cores. In this paper, the review on advanced technologies for modeling, power and load following control of Reactor Cores is presented. Modeling approaches for Reactor Cores are reviewed such as the point Reactor Core modeling. Power control methods for Reactor Cores are reviewed such as the feedback control with a state observer. Load following control techniques for Reactor Cores are reviewed such as Mode A, Mode G, Mode T, Mechanical Shim and advanced control methods of containing multivariable frequency control, etc. The review in this paper can contribute to comprehend the past work with respective advantages, and then exploit novel research directions for development of nuclear power plants.
Kenton - One of the best experts on this subject based on the ideXlab platform.
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Termination of light-water Reactor Core-melt accidents with a chemical Core catcher: the Core-melt source reduction system (COMSORS)
1996Co-Authors: Charles W. Forsberg, G.w. Parker, J.c. Rudolph, I.w. Osborne-lee, KentonAbstract:The Core-Melt Source Reduction System (COMSORS) is a new approach to terminate light-water Reactor Core melt accidents and ensure containment integrity. A special dissolution glass is placed under the Reactor vessel. If Core debris is released onto the glass, the glass melts and the debris dissolves into the molten glass, thus creating a homogeneous molten glass. The molten glass, with dissolved Core debris, spreads into a wide pool, distributing the heat for removal by radiation to the Reactor cavity above or by transfer to water on top of the molten glass. Expected equilibrium glass temperatures are approximately 600 degrees C. The creation of a low-temperature, homogeneous molten glass with known geometry permits cooling of the glass without threatening containment integrity. This report describes the technology, initial experiments to measure key glass properties, and modeling of COMSORS operations.
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Termination of light-water Reactor Core-melt accidents with a chemical Core catcher: the Core-melt source reduction system (COMSORS)
1996Co-Authors: Charles W. Forsberg, G.w. Parker, J.c. Rudolph, I.w. Osborne-lee, KentonAbstract:The Core-Melt Source Reduction System (COMSORS) is a new approach to terminate light-water Reactor Core melt accidents and ensure containment integrity. A special dissolution glass is placed under the Reactor vessel. If Core debris is released onto the glass, the glass melts and the debris dissolves into the molten glass, thus creating a homogeneous molten glass. The molten glass, with dissolved Core debris, spreads into a wide pool, distributing the heat for removal by radiation to the Reactor cavity above or by transfer to water on top of the molten glass. Expected equilibrium glass temperatures are approximately 600 degrees C. The creation of a low-temperature, homogeneous molten glass with known geometry permits cooling of the glass without threatening containment integrity. This report describes the technology, initial experiments to measure key glass properties, and modeling of COMSORS operations.
