System Modeling for Transient Analysis of Loop-type Liquid-metal-cooled Fast Breeder Reactors

System Modeling for Transient Analysis of Loop-type Liquid-metal-cooled Fast Breeder Reactors PDF Author: Mohsen Khatib-Rahbar
Publisher:
ISBN:
Category : Liquid metal cooled reactors
Languages : en
Pages : 786

Get Book Here

Book Description

System Modeling for Transient Analysis of Loop-type Liquid-metal-cooled Fast Breeder Reactors

System Modeling for Transient Analysis of Loop-type Liquid-metal-cooled Fast Breeder Reactors PDF Author: Mohsen Khatib-Rahbar
Publisher:
ISBN:
Category : Liquid metal cooled reactors
Languages : en
Pages : 786

Get Book Here

Book Description


Transient Analysis of the Primary System of a Liquid Metal-cooled Fast Breeder Reactor Plant

Transient Analysis of the Primary System of a Liquid Metal-cooled Fast Breeder Reactor Plant PDF Author: Grigore F. Pavlenco
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 740

Get Book Here

Book Description


Systems Modeling for a Pool-type Liquid Metal-cooled Fast Breeder Reactor

Systems Modeling for a Pool-type Liquid Metal-cooled Fast Breeder Reactor PDF Author: John R. Raber
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 780

Get Book Here

Book Description


Dynamic Simulation of Sodium Cooled Fast Reactors

Dynamic Simulation of Sodium Cooled Fast Reactors PDF Author: G Vaidyanathan
Publisher: CRC Press
ISBN: 1000779564
Category : Technology & Engineering
Languages : en
Pages : 289

Get Book Here

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

Thermal Analysis of Liquid-metal Fast Breeder Reactors PDF Author: Yu S. Tang
Publisher: American Nuclear Society
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 432

Get Book Here

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

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1744

Get Book Here

Book Description


NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 104

Get Book Here

Book Description


LMFBR

LMFBR PDF Author: Argonne National Laboratory
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 368

Get Book Here

Book Description


Simulation of a Liquid Metal Fast Breeder Reactor on a Hybrid Computer

Simulation of a Liquid Metal Fast Breeder Reactor on a Hybrid Computer PDF Author: Charles Lee Keller
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 85

Get Book Here

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).

Liquid Metal Cooled Reactors

Liquid Metal Cooled Reactors PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201079077
Category : Liquid metal cooled reactors
Languages : en
Pages : 0

Get Book Here

Book Description
Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.