General and Reactor Development Program
Title | General and Reactor Development Program PDF eBook |
Author | United States. Congress. Joint Committee on Atomic Energy |
Publisher | |
Pages | 940 |
Release | 1968 |
Genre | |
ISBN |
Structural Materials for Generation IV Nuclear Reactors
Title | Structural Materials for Generation IV Nuclear Reactors PDF eBook |
Author | Pascal Yvon |
Publisher | Woodhead Publishing |
Pages | 686 |
Release | 2016-08-27 |
Genre | Technology & Engineering |
ISBN | 0081009127 |
Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area
Reactor development program (excluding civilian power program), February 8, 9, 10, and April 8, 1965
Title | Reactor development program (excluding civilian power program), February 8, 9, 10, and April 8, 1965 PDF eBook |
Author | United States. Congress. Joint Committee on Atomic Energy |
Publisher | |
Pages | 508 |
Release | 1965 |
Genre | Nuclear energy |
ISBN |
Reactor development program (civilian power program)
Title | Reactor development program (civilian power program) PDF eBook |
Author | United States. Congress. Joint Committee on Atomic Energy |
Publisher | |
Pages | 662 |
Release | 1965 |
Genre | Nuclear energy |
ISBN |
U.S. Research Reactors
Title | U.S. Research Reactors PDF eBook |
Author | Battelle Memorial Institute. Columbus Laboratories |
Publisher | |
Pages | 80 |
Release | 1957 |
Genre | Nuclear energy |
ISBN |
Liquid Metal Cooled Reactors
Title | Liquid Metal Cooled Reactors PDF eBook |
Author | International Atomic Energy Agency |
Publisher | |
Pages | 0 |
Release | 2007 |
Genre | Liquid metal cooled reactors |
ISBN | 9789201079077 |
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.
Dynamics and Control of Nuclear Reactors
Title | Dynamics and Control of Nuclear Reactors PDF eBook |
Author | Thomas W. Kerlin |
Publisher | Academic Press |
Pages | 404 |
Release | 2019-10-05 |
Genre | Technology & Engineering |
ISBN | 0128152621 |
Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on small modular reactors, sodium fast reactors, and gas-cooled reactors. - Provides case studies and examples to demonstrate learning through problem solving, including an analysis of accidents at Three Mile Island, Chernobyl and Fukushima Daiichi - Includes MATLAB codes to enable the reader to apply the knowledge gained to their own projects and research - Features examples and problems that illustrate the principles of dynamic analysis as well as the mathematical tools necessary to understand and apply the analysis Publishers Note: Table 3.1 has been revised and will be included in future printings of the book with the following data: Group Decay Constant, li (sec-1) Delayed Neutron Fraction (bi) 1 0.0124 0.000221 2 0.0305 0.001467 3 0.111 0.001313 4 0.301 0.002647 5 1.14 0.000771 6 3.01 0.000281 Total delayed neutron fraction: 0.0067