Advanced Test Reactor Critical Experiments
Author : A. L. MacKinney
Publisher :
Page : 476 pages
File Size : 42,14 MB
Release : 1963
Category : Engineering test reactors
ISBN :
Author : A. L. MacKinney
Publisher :
Page : 476 pages
File Size : 42,14 MB
Release : 1963
Category : Engineering test reactors
ISBN :
Author : International Atomic Energy Agency
Publisher : International Atomic Energy Agency
Page : 108 pages
File Size : 23,33 MB
Release : 2014
Category : Science
ISBN : 9789201450104
This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.
Author : Robert A. Turner
Publisher :
Page : 50 pages
File Size : 13,11 MB
Release : 1964
Category : Nuclear reactors
ISBN :
Author : Tetsuaki Takeda
Publisher : Academic Press
Page : 500 pages
File Size : 19,99 MB
Release : 2021-02-24
Category : Technology & Engineering
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 : Pascal Yvon
Publisher : Woodhead Publishing
Page : 686 pages
File Size : 32,61 MB
Release : 2016-08-27
Category : 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
Author : National Academies of Sciences, Engineering, and Medicine
Publisher : National Academies Press
Page : 205 pages
File Size : 46,61 MB
Release : 2016-02-12
Category : Science
ISBN : 0309379210
The continued presence of highly enriched uranium (HEU) in civilian installations such as research reactors poses a threat to national and international security. Minimization, and ultimately elimination, of HEU in civilian research reactors worldwide has been a goal of U.S. policy and programs since 1978. Today, 74 civilian research reactors around the world, including 8 in the United States, use or are planning to use HEU fuel. Since the last National Academies of Sciences, Engineering, and Medicine report on this topic in 2009, 28 reactors have been either shut down or converted from HEU to low enriched uranium fuel. Despite this progress, the large number of remaining HEU-fueled reactors demonstrates that an HEU minimization program continues to be needed on a worldwide scale. Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors assesses the status of and progress toward eliminating the worldwide use of HEU fuel in civilian research and test reactors.
Author :
Publisher :
Page : 144 pages
File Size : 29,99 MB
Release : 1963
Category : Nuclear reactors
ISBN :
Author : United States. Congress. Joint Committee on Atomic Energy
Publisher :
Page : 1374 pages
File Size : 14,19 MB
Release : 1975
Category :
ISBN :
Author : United States. Congress. Joint Committee ...
Publisher :
Page : 2166 pages
File Size : 36,80 MB
Release : 1964
Category :
ISBN :
Author :
Publisher :
Page : 28 pages
File Size : 24,15 MB
Release : 1960-06
Category : Nuclear reactors
ISBN :