Author: Helium Breeder Associates
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 13
Book Description
Executive Summary of the Gas-cooled Fast Breeder Reactor Commercialization Study
Author: Helium Breeder Associates
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 13
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 13
Book Description
A Study of a Gas-cooled Fast Breeder Reactor
Author:
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 274
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 274
Book Description
Gas-cooled Fast Breeder Reactor Commercialization Study for U.S. Energy Research and Development Administration
Author: Helium Breeder Associates
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages :
Book Description
The Fast Breeder Reactor Decision
Author: Mark F. Sharefkin
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 44
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 44
Book Description
Appendices for the Gas-cooled Fast Breeder Reactor Commercialization Study
Author: Helium Breeder Associates
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages :
Book Description
Status of Fast Reactor Research and Technology Development
Author: International Atomic Energy Agency
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
An Evaluation of the Gas Cooled Fast Reactor
Author: U.S. Atomic Energy Commission. Division of Reactor Development and Technology
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 56
Book Description
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 56
Book Description
An Evaluation of Gas-cooled Fast Reactor
Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 260
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 260
Book Description
Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor
Author: Willem Frederik Geert van Rooijen
Publisher: IOS Press
ISBN: 9781586036966
Category : Technology & Engineering
Languages : en
Pages : 160
Book Description
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Publisher: IOS Press
ISBN: 9781586036966
Category : Technology & Engineering
Languages : en
Pages : 160
Book Description
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Nuclear Proliferation and Civilian Nuclear Power. Executive Summary
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 80
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 80
Book Description