Gas Cooled Ceramic Power Breeder Reactor

Gas Cooled Ceramic Power Breeder Reactor

Author: J. F. Smith (Jr.)

Publisher:

Published: 1954

Total Pages: 226

ISBN-13:

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Book Synopsis Gas Cooled Ceramic Power Breeder Reactor by : J. F. Smith (Jr.)

Download or read book Gas Cooled Ceramic Power Breeder Reactor written by J. F. Smith (Jr.) and published by . This book was released on 1954 with total page 226 pages. Available in PDF, EPUB and Kindle. Book excerpt:


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

Author: Willem Frederik Geert van Rooijen

Publisher: IOS Press

Published: 2006

Total Pages: 160

ISBN-13: 9781586036966

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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.


Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen

Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 Alternate Coolant Fast Breeder Reactors

An Evaluation of Alternate Coolant Fast Breeder Reactors

Author: United States. Alternate Coolant Task Force

Publisher:

Published: 1969

Total Pages: 170

ISBN-13:

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Book Synopsis An Evaluation of Alternate Coolant Fast Breeder Reactors by : United States. Alternate Coolant Task Force

Download or read book An Evaluation of Alternate Coolant Fast Breeder Reactors written by United States. Alternate Coolant Task Force and published by . This book was released on 1969 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt:


Civilian Power Reactor Program

Civilian Power Reactor Program

Author: U.S. Atomic Energy Commission

Publisher:

Published: 1960

Total Pages: 96

ISBN-13:

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Book Synopsis Civilian Power Reactor Program by : U.S. Atomic Energy Commission

Download or read book Civilian Power Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:


Semi-homogeneous High-temperature Gas-cooled Breeder Reactors

Semi-homogeneous High-temperature Gas-cooled Breeder Reactors

Author: K. Inoue

Publisher:

Published: 1962

Total Pages: 94

ISBN-13:

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Book Synopsis Semi-homogeneous High-temperature Gas-cooled Breeder Reactors by : K. Inoue

Download or read book Semi-homogeneous High-temperature Gas-cooled Breeder Reactors written by K. Inoue and published by . This book was released on 1962 with total page 94 pages. Available in PDF, EPUB and Kindle. Book excerpt:


An Evaluation of Gas-cooled Fast Reactor[s]

An Evaluation of Gas-cooled Fast Reactor[s]

Author: Oak Ridge National Laboratory

Publisher:

Published: 1969

Total Pages: 260

ISBN-13:

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Book Synopsis An Evaluation of Gas-cooled Fast Reactor[s] by : Oak Ridge National Laboratory

Download or read book An Evaluation of Gas-cooled Fast Reactor[s] written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 260 pages. Available in PDF, EPUB and Kindle. Book excerpt:


Gas-cooled Nuclear Reactors

Gas-cooled Nuclear Reactors

Author: France. Commissariat à l'énergie atomique

Publisher:

Published: 2006

Total Pages: 192

ISBN-13:

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Book Synopsis Gas-cooled Nuclear Reactors by : France. Commissariat à l'énergie atomique

Download or read book Gas-cooled Nuclear Reactors written by France. Commissariat à l'énergie atomique and published by . This book was released on 2006 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:


Fast Breeder Reactors

Fast Breeder Reactors

Author: P. V. Evans

Publisher: Elsevier

Published: 2013-10-15

Total Pages: 961

ISBN-13: 1483223442

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Fast Breeder Reactors covers the proceedings of the 1966 London Conference on Fast Breeder Reactors, organized by the British Nuclear Energy Society. This conference highlights the technical and commercial aspects of nuclear power. This book is organized into five sections encompassing 37 chapters. The introductory section considers the historical development of British nuclear power technology and its application. This section provides an introduction to the principles of fast breeder reactor. The succeeding sections look into the mode of operation, and the design and physical aspects of prototype fast reactor. These sections also consider the theoretical and experimental works of these reactors in the United States. A description of the irradiation behavior of plutonium-bearing ceramic fuel pins is also included. The concluding section explores the control and instrumentation of the prototype fast reactor. This section specifically evaluates the main engineering equipment and the experimental work carried out in support of the selected designs, and to an explanation of certain problems of sodium technology. The design and experimental works on the main circulating pumps, the intermediate heat exchanger, and the steam generator are also surveyed. This book will prove useful to nuclear physicists, design engineers, and research workers who are interested in nuclear power-related fields.


Book Synopsis Fast Breeder Reactors by : P. V. Evans

Download or read book Fast Breeder Reactors written by P. V. Evans and published by Elsevier. This book was released on 2013-10-15 with total page 961 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fast Breeder Reactors covers the proceedings of the 1966 London Conference on Fast Breeder Reactors, organized by the British Nuclear Energy Society. This conference highlights the technical and commercial aspects of nuclear power. This book is organized into five sections encompassing 37 chapters. The introductory section considers the historical development of British nuclear power technology and its application. This section provides an introduction to the principles of fast breeder reactor. The succeeding sections look into the mode of operation, and the design and physical aspects of prototype fast reactor. These sections also consider the theoretical and experimental works of these reactors in the United States. A description of the irradiation behavior of plutonium-bearing ceramic fuel pins is also included. The concluding section explores the control and instrumentation of the prototype fast reactor. This section specifically evaluates the main engineering equipment and the experimental work carried out in support of the selected designs, and to an explanation of certain problems of sodium technology. The design and experimental works on the main circulating pumps, the intermediate heat exchanger, and the steam generator are also surveyed. This book will prove useful to nuclear physicists, design engineers, and research workers who are interested in nuclear power-related fields.


Steam-cooled Power-reactor Evaluation

Steam-cooled Power-reactor Evaluation

Author:

Publisher:

Published: 1961

Total Pages: 90

ISBN-13:

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Book Synopsis Steam-cooled Power-reactor Evaluation by :

Download or read book Steam-cooled Power-reactor Evaluation written by and published by . This book was released on 1961 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt:


An Evaluation of the Gas Cooled Fast Reactor

An Evaluation of the Gas Cooled Fast Reactor

Author: U.S. Atomic Energy Commission. Division of Reactor Development and Technology

Publisher:

Published: 1972

Total Pages: 56

ISBN-13:

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Book Synopsis An Evaluation of the Gas Cooled Fast Reactor by : U.S. Atomic Energy Commission. Division of Reactor Development and Technology

Download or read book An Evaluation of the Gas Cooled Fast Reactor written by U.S. Atomic Energy Commission. Division of Reactor Development and Technology and published by . This book was released on 1972 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: