Exposure of Reactor Structural Materials to Impure Helium at Elevated Temperatures

Exposure of Reactor Structural Materials to Impure Helium at Elevated Temperatures
Author:
Publisher:
Total Pages:
Release: 1962
Genre:
ISBN:

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In the High-temperature Gas-cooled Reactor (HTGR), structural metals will be required to operate at temperatures of 1000 to 1400 deg F in an impure- helium environment for extended periods of time. Six candidate materials for such applications, including nickel alloys and stainless steels, were subjected to simulated reactor environments for times up to 3000 hr to evaluate the extent of corrosion and the changes in mechanical properties occasioned by I such exposures. Under the experimental exposure conditions (helium containing 200 to 300 ppm CO and 200 to 300 ppm H/sub 2/, or helium containing 2000 to 3000 ppm CO and 2000 to 3000 ppm H/sub 2/, at temperatures of 1200 or 1400 deg F), oxidation rather than carburization appears to be the major corrosion process; however, in some cases alternating carburization and decarburization were observed. Measurements of weight gains are described. None of the materials studied exhibited a large change in their mechanical properties after exposures at 1200 deg F. After exposures at 1400 deg F, moderate changes in mechanical properties were observed for all materials except Type 321H stainless steel, which exhibited a large decrease in ductility after l500-hr exposure to the higher impurity concentration. In general, the control specimens were affected as greatly as the specimens exposed to the impure helium environments, under the conditions of these tests. (R.J.S.).

Helium

Helium
Author:
Publisher:
Total Pages: 1308
Release: 1970
Genre: Helium
ISBN:

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Helium

Helium
Author: Philip Cochran Tully
Publisher:
Total Pages: 876
Release: 1970
Genre: Alpha rays
ISBN:

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Structural Materials for Generation IV Nuclear Reactors

Structural Materials for Generation IV Nuclear Reactors
Author: Pascal Yvon
Publisher: Woodhead Publishing
Total Pages: 686
Release: 2016-08-27
Genre: Technology & Engineering
ISBN: 0081009127

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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

Energy Research Abstracts

Energy Research Abstracts
Author:
Publisher:
Total Pages: 946
Release: 1990
Genre: Power resources
ISBN:

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Information Circular

Information Circular
Author:
Publisher:
Total Pages: 1100
Release: 1970
Genre: Mines and mineral resources
ISBN:

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Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports
Author:
Publisher:
Total Pages: 666
Release: 1982
Genre: Aeronautics
ISBN:

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Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.

Information Circular

Information Circular
Author: United States. Bureau of Mines
Publisher:
Total Pages: 1034
Release: 1970
Genre: Mine safety
ISBN:

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High Temperature Gas-cooled Reactors

High Temperature Gas-cooled Reactors
Author: Tetsuaki Takeda
Publisher: Academic Press
Total Pages: 478
Release: 2021-02-24
Genre: Business & Economics
ISBN: 012821032X

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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.