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Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor PDF 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.

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor PDF 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.

An Evaluation of Gas-cooled Fast Reactor

An Evaluation of Gas-cooled Fast Reactor PDF Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 260

Book Description


An Evaluation of Alternate Coolant Fast Breeder Reactors

An Evaluation of Alternate Coolant Fast Breeder Reactors PDF Author: United States. Alternate Coolant Task Force
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 170

Book Description


A Study of a Gas-cooled Fast Breeder Reactor

A Study of a Gas-cooled Fast Breeder Reactor PDF Author:
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 274

Book Description


An Evaluation of Steam-cooled Fast Breeder Reactors

An Evaluation of Steam-cooled Fast Breeder Reactors PDF Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 378

Book Description


Gas-cooled Fast Breeder Reactor

Gas-cooled Fast Breeder Reactor PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 162

Book Description


Gas Cooled Fast Reactor

Gas Cooled Fast Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 46

Book Description
Although most of the development work on fast breeder reactors has been devoted to the use of liquid metal cooling, interest has been expressed for a number of years in alternative breeder concepts using other coolants. One of a number of concepts in which interest has been retained is the Gas-Cooled Fast Reactor (GCFR). As presently envisioned, it would operate on the uranium-plutonium mixed oxide fuel cycle, similar to that used in the Liquid Metal Fast Breeder Reactor (LMFBR), and would use helium gas as the coolant.

An Evaluation of the Gas Cooled Fast Reactor

An Evaluation of the Gas Cooled Fast Reactor PDF Author: U.S. Atomic Energy Commission. Division of Reactor Development and Technology
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 56

Book Description


Fast Breeder Reactors

Fast Breeder Reactors PDF Author: Alan Edward Waltar
Publisher: Alan E. Waltar
ISBN: 0080259839
Category : Breeder, reactors
Languages : en
Pages : 877

Book Description


Storage and Hybridization of Nuclear Energy

Storage and Hybridization of Nuclear Energy PDF Author: Hitesh Bindra
Publisher: Academic Press
ISBN: 0128139765
Category : Science
Languages : en
Pages : 300

Book Description
Storage and Hybridization of Nuclear Energy: Techno-economic Integration of Renewable and Nuclear Energy provides a unique analysis of the storage and hybridization of nuclear and renewable energy. Editor Bindra and his team of expert contributors present various global methodologies to obtain the techno-economic feasibility of the integration of storage or hybrid cycles in nuclear power plants. Aimed at those studying, researching and working in the nuclear engineering field, this book offers nuclear reactor technology vendors, nuclear utilities workers and regulatory commissioners a very unique resource on how to access reliable, flexible and clean energy from variable-generation. Presents a unique view on the technologies and systems available to integrate renewables and nuclear energy Provides insights into the different methodologies and technologies currently available for the storage of energy Includes case studies from well-known experts working on specific integration concepts around the world