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Response of a Helium-Cooled Fast Reactor to Changes in Coolant Flow and Reactivity

Response of a Helium-Cooled Fast Reactor to Changes in Coolant Flow and Reactivity PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 26

Book Description


Response of a Helium-Cooled Fast Reactor to Changes in Coolant Flow and Reactivity

Response of a Helium-Cooled Fast Reactor to Changes in Coolant Flow and Reactivity PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 26

Book Description


Response of a Helium-cooled Fast Reactor to Changes in Coolant Flow and Reactivity

Response of a Helium-cooled Fast Reactor to Changes in Coolant Flow and Reactivity PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


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


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 912

Book Description


Thermal and Flow Design of Helium-cooled Reactors

Thermal and Flow Design of Helium-cooled Reactors PDF Author: Gilbert Melese
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 444

Book Description
This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.

Conference on Neutron Cross Section Technology

Conference on Neutron Cross Section Technology PDF Author: P. B. Hemmig
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 582

Book Description


AEC Research and Development Report

AEC Research and Development Report PDF Author: Atomic Energy Commission
Publisher:
ISBN:
Category :
Languages : en
Pages : 382

Book Description


Publications, Reports, and Papers for 1965 from Oak Ridge National Laboratory

Publications, Reports, and Papers for 1965 from Oak Ridge National Laboratory PDF Author: K.O. Johnsson
Publisher:
ISBN:
Category : Technical reports
Languages : en
Pages : 356

Book Description


Publications, Reports, and Papers for 1966 from Oak Ridge National Laboratory

Publications, Reports, and Papers for 1966 from Oak Ridge National Laboratory PDF Author: F. M. O'Hara
Publisher:
ISBN:
Category : Technical reports
Languages : en
Pages : 374

Book Description