Gas Cooled Reactors Today Advances In Fuel Core And Structural Materials

Gas Cooled Reactors Today Advances In Fuel Core And Structural Materials Book in PDF, ePub and Kindle version is available to download in english. Read online anytime anywhere directly from your device. Click on the download button below to get a free pdf file of Gas Cooled Reactors Today Advances In Fuel Core And Structural Materials book. This book definitely worth reading, it is an incredibly well-written.

Structural Materials for Generation IV Nuclear Reactors

Author : Pascal Yvon
Publisher : Woodhead Publishing
Page : 684 pages
File Size : 54,5 Mb
Release : 2016-08-27
Category : Technology & Engineering
ISBN : 9780081009123

Get Book

Structural Materials for Generation IV Nuclear Reactors by Pascal Yvon Pdf

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

High Temperature Gas-cooled Reactors

Author : Tetsuaki Takeda,Yoshiyuki Inagaki
Publisher : Academic Press
Page : 478 pages
File Size : 44,6 Mb
Release : 2021-02-24
Category : Business & Economics
ISBN : 9780128210321

Get Book

High Temperature Gas-cooled Reactors by Tetsuaki Takeda,Yoshiyuki Inagaki Pdf

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.

Energy Research Abstracts

Author : Anonim
Publisher : Unknown
Page : 1200 pages
File Size : 45,9 Mb
Release : 1986
Category : Power resources
ISBN : MSU:31293010868556

Get Book

Energy Research Abstracts by Anonim Pdf

ERDA Energy Research Abstracts

Author : Anonim
Publisher : Unknown
Page : 668 pages
File Size : 48,8 Mb
Release : 1983
Category : Power resources
ISBN : UIUC:30112018073731

Get Book

ERDA Energy Research Abstracts by Anonim Pdf

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

Author : Willem Frederik Geert van Rooijen
Publisher : IOS Press
Page : 160 pages
File Size : 49,8 Mb
Release : 2006
Category : Technology & Engineering
ISBN : 1586036963

Get Book

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

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.

INIS Atomindex

Author : Anonim
Publisher : Unknown
Page : 1378 pages
File Size : 48,7 Mb
Release : 1984
Category : Nuclear energy
ISBN : MINN:31951D00544768M

Get Book

INIS Atomindex by Anonim Pdf

Handbook of Advanced Ceramics

Author : Anonim
Publisher : Academic Press
Page : 1258 pages
File Size : 55,6 Mb
Release : 2013-04-11
Category : Technology & Engineering
ISBN : 9780123854704

Get Book

Handbook of Advanced Ceramics by Anonim Pdf

This new handbook will be an essential resource for ceramicists. It includes contributions from leading researchers around the world and includes sections on Basic Science of Advanced Ceramics, Functional Ceramics (electro-ceramics and optoelectro-ceramics) and engineering ceramics. Contributions from more than 50 leading researchers from around the world Covers basic science of advanced ceramics, functional ceramics (electro-ceramics and optoelectro-ceramics), and engineering ceramics Approximately 750 illustrations

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 639 pages
File Size : 50,9 Mb
Release : 2012-06
Category : Business & Economics
ISBN : 9201253109

Get Book

Advances in High Temperature Gas Cooled Reactor Fuel Technology by International Atomic Energy Agency Pdf

This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

ERDA Energy Research Abstracts

Author : United States. Energy Research and Development Administration
Publisher : Unknown
Page : 772 pages
File Size : 47,5 Mb
Release : 1976
Category : Medicine
ISBN : UOM:39015048721529

Get Book

ERDA Energy Research Abstracts by United States. Energy Research and Development Administration Pdf

Nuclear Science Abstracts

Author : Anonim
Publisher : Unknown
Page : 722 pages
File Size : 52,7 Mb
Release : 1976-02
Category : Nuclear energy
ISBN : PSU:000047758872

Get Book

Nuclear Science Abstracts by Anonim Pdf

The ORNL Gas-cooled Reactor

Author : Oak Ridge National Laboratory
Publisher : Unknown
Page : 102 pages
File Size : 43,8 Mb
Release : 1958
Category : Gas cooled reactors
ISBN : UOM:39015077310608

Get Book

The ORNL Gas-cooled Reactor by Oak Ridge National Laboratory Pdf

Advanced Si-Based Ceramics and Composites

Author : Hai Doo Kim,Hua Tay Lin,Michael J. Hoffmann
Publisher : Trans Tech Publications Ltd
Page : 520 pages
File Size : 48,6 Mb
Release : 2005-06-15
Category : Technology & Engineering
ISBN : 9783038130178

Get Book

Advanced Si-Based Ceramics and Composites by Hai Doo Kim,Hua Tay Lin,Michael J. Hoffmann Pdf

Volume is indexed by Thomson Reuters CPCI-S (WoS). Significant progress has been made over the past 30 years in handling silicon-based ceramics such as silicon nitride, silicon carbide, SiAlON, silicides and composites. A better understanding of processing parameters in various forming techniques, and of microstructure-property relationships, has led to substantial improvements in thermomechanical performance and reliability; as well as in cost reduction.