Author: Mohsen Khatib-Rahbar
Publisher:
ISBN:
Category : Liquid metal cooled reactors
Languages : en
Pages : 786
Book Description
System Modeling for Transient Analysis of Loop-type Liquid-metal-cooled Fast Breeder Reactors
Author: Mohsen Khatib-Rahbar
Publisher:
ISBN:
Category : Liquid metal cooled reactors
Languages : en
Pages : 786
Book Description
Publisher:
ISBN:
Category : Liquid metal cooled reactors
Languages : en
Pages : 786
Book Description
Transient Analysis of the Primary System of a Liquid Metal-cooled Fast Breeder Reactor Plant
Author: Grigore F. Pavlenco
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 740
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 740
Book Description
Systems Modeling for a Pool-type Liquid Metal-cooled Fast Breeder Reactor
Author: John R. Raber
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 780
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 780
Book Description
Dynamic Simulation of Sodium Cooled Fast Reactors
Author: G Vaidyanathan
Publisher: CRC Press
ISBN: 1000779564
Category : Technology & Engineering
Languages : en
Pages : 289
Book Description
This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor. The book • Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium. • Compares different numerical techniques and brings out the best one for the solution of the models. • Provides a methodology of validation based on experiments. • Examines modeling and simulation aspects necessary for the safe design of a fast reactor. • Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems. • Discusses the application of the models to the design of a sodium-cooled fast reactor It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.
Publisher: CRC Press
ISBN: 1000779564
Category : Technology & Engineering
Languages : en
Pages : 289
Book Description
This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor. The book • Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium. • Compares different numerical techniques and brings out the best one for the solution of the models. • Provides a methodology of validation based on experiments. • Examines modeling and simulation aspects necessary for the safe design of a fast reactor. • Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems. • Discusses the application of the models to the design of a sodium-cooled fast reactor It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.
Thermal Analysis of Liquid-metal Fast Breeder Reactors
Author: Yu S. Tang
Publisher: American Nuclear Society
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 432
Book Description
This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.
Publisher: American Nuclear Society
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 432
Book Description
This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1744
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1744
Book Description
LMFBR
Author: Argonne National Laboratory
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 368
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 368
Book Description
Simulation of a Liquid Metal Fast Breeder Reactor on a Hybrid Computer
Author: Charles Lee Keller
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 85
Book Description
A Liquid Metal Fast Breeder Reactor is simulated on a hybrid computer to study the transient behavior of the neutron density during a controlled reactivity input disturbance. The nonlinear partial differential equations of heat flow are reduced by a discrete space-continuous time method to ordinary nonlinear differential equations which are readily solved on the analog computer. Use is made of time multiplexing of the analog circuitry in order to reduce the number of components. An open-loop iteration process is employed to solve the closed-loop feedback system. Recently conducted research with the open-loop iteration method has demonstrated that a large number of iterations are required for convergence. An algorithm is developed which gives an improvement in the convergence rate for early values of time. For times greater than two seconds a stability problem with the converged solution was encountered and is discussed with some observations and comments. Innovations are introduced in the simulation of the neutron kinetics equations and in the handling of the nonlinear thermal properties of the uranium oxide fuel. (Author).
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 85
Book Description
A Liquid Metal Fast Breeder Reactor is simulated on a hybrid computer to study the transient behavior of the neutron density during a controlled reactivity input disturbance. The nonlinear partial differential equations of heat flow are reduced by a discrete space-continuous time method to ordinary nonlinear differential equations which are readily solved on the analog computer. Use is made of time multiplexing of the analog circuitry in order to reduce the number of components. An open-loop iteration process is employed to solve the closed-loop feedback system. Recently conducted research with the open-loop iteration method has demonstrated that a large number of iterations are required for convergence. An algorithm is developed which gives an improvement in the convergence rate for early values of time. For times greater than two seconds a stability problem with the converged solution was encountered and is discussed with some observations and comments. Innovations are introduced in the simulation of the neutron kinetics equations and in the handling of the nonlinear thermal properties of the uranium oxide fuel. (Author).
NUREG/CR.
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 104
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 104
Book Description
Simulation of a Liquid Metal Fast Breeder Reactor on a Hybrid Computer
Author:
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 0
Book Description
A Liquid Metal Fast Breeder Reactor is simulated on a hybrid computer to study the transient behavior of the neutron density during a controlled reactivity input disturbance. The nonlinear partial differential equations of heat flow are reduced by a discrete space-continuous time method to ordinary nonlinear differential equations which are readily solved on the analog computer. Use is made of time multiplexing of the analog circuitry in order to reduce the number of components. An open-loop iteration process is employed to solve the closed-loop feedback system. Recently conducted research with the open-loop iteration method has demonstrated that a large number of iterations are required for convergence. An algorithm is developed which gives an improvement in the convergence rate for early values of time. For times greater than two seconds a stability problem with the converged solution was encountered and is discussed with some observations and comments. Innovations are introduced in the simulation of the neutron kinetics equations and in the handling of the nonlinear thermal properties of the uranium oxide fuel. (Author).
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 0
Book Description
A Liquid Metal Fast Breeder Reactor is simulated on a hybrid computer to study the transient behavior of the neutron density during a controlled reactivity input disturbance. The nonlinear partial differential equations of heat flow are reduced by a discrete space-continuous time method to ordinary nonlinear differential equations which are readily solved on the analog computer. Use is made of time multiplexing of the analog circuitry in order to reduce the number of components. An open-loop iteration process is employed to solve the closed-loop feedback system. Recently conducted research with the open-loop iteration method has demonstrated that a large number of iterations are required for convergence. An algorithm is developed which gives an improvement in the convergence rate for early values of time. For times greater than two seconds a stability problem with the converged solution was encountered and is discussed with some observations and comments. Innovations are introduced in the simulation of the neutron kinetics equations and in the handling of the nonlinear thermal properties of the uranium oxide fuel. (Author).