Development of a Simulated High-temperature Nuclear Loop
Author | : James P. McGee |
Publisher | : |
Total Pages | : 28 |
Release | : 1960 |
Genre | : Heat |
ISBN | : |
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Author | : James P. McGee |
Publisher | : |
Total Pages | : 28 |
Release | : 1960 |
Genre | : Heat |
ISBN | : |
Author | : Aaron G. Starliper |
Publisher | : |
Total Pages | : 578 |
Release | : 1961 |
Genre | : Aluminum silicates |
ISBN | : |
Author | : Neil H. Coates |
Publisher | : |
Total Pages | : 24 |
Release | : 1961 |
Genre | : Nuclear engineering |
ISBN | : |
Author | : James P. MacGee |
Publisher | : |
Total Pages | : 17 |
Release | : 1960 |
Genre | : |
ISBN | : |
Author | : Tetsuaki Takeda |
Publisher | : Academic Press |
Total Pages | : 478 |
Release | : 2021-02-24 |
Genre | : Business & Economics |
ISBN | : 012821032X |
High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.
Author | : |
Publisher | : |
Total Pages | : 638 |
Release | : 1962 |
Genre | : Mines and mineral resources |
ISBN | : |
Author | : United States. Bureau of Mines |
Publisher | : |
Total Pages | : 708 |
Release | : 1960 |
Genre | : Mine safety |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : 766 |
Release | : 1961 |
Genre | : Mineral industries |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : 658 |
Release | : 1976 |
Genre | : Nuclear energy |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1977 |
Genre | : |
ISBN | : |
Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (impure Helium), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes progress to date on alloy selection for VHTR Nuclear Process Heat (NPH) applications and for DCHT applications. The present status on the simulated reactor helium loop design and on designs for the testing and analysis facilities and equipment is discussed.