Author: International Atomic Energy Agency
Publisher: International Atomic Energy Agency
ISBN: 9789201010186
Category : Technology & Engineering
Languages : en
Pages : 52
Book Description
This publication presents both an overview and detailed information on more than 150 experimental facilities being used for developing and deploying innovative liquid metal-cooled (sodium, lead and lead-bismuth) fast neutron systems, both critical and subcritical. Facilities, both under construction and those in operation are considered. It is expected that by providing the end users with detailed information on existing and future experimental facilities able to support innovative liquid metal cooled fast neutron systems, the publication will facilitate cooperation between organizations and knowledge transfer. An overview of the existing and future experimental facilities is presented in the body text of this publication. The profiles of all facilities in the form of individual papers are available on the attached CD-ROM and in the related on-line database maintained by the IAEA Catalogue of Facilities in Support of Liquid Metal-cooled Fast Neutron Systems (LMFNS Catalogue).
Experimental Facilities in Support of Liquid Metal Cooled Fast Neutron Systems
Author: International Atomic Energy Agency
Publisher: International Atomic Energy Agency
ISBN: 9789201010186
Category : Technology & Engineering
Languages : en
Pages : 52
Book Description
This publication presents both an overview and detailed information on more than 150 experimental facilities being used for developing and deploying innovative liquid metal-cooled (sodium, lead and lead-bismuth) fast neutron systems, both critical and subcritical. Facilities, both under construction and those in operation are considered. It is expected that by providing the end users with detailed information on existing and future experimental facilities able to support innovative liquid metal cooled fast neutron systems, the publication will facilitate cooperation between organizations and knowledge transfer. An overview of the existing and future experimental facilities is presented in the body text of this publication. The profiles of all facilities in the form of individual papers are available on the attached CD-ROM and in the related on-line database maintained by the IAEA Catalogue of Facilities in Support of Liquid Metal-cooled Fast Neutron Systems (LMFNS Catalogue).
Publisher: International Atomic Energy Agency
ISBN: 9789201010186
Category : Technology & Engineering
Languages : en
Pages : 52
Book Description
This publication presents both an overview and detailed information on more than 150 experimental facilities being used for developing and deploying innovative liquid metal-cooled (sodium, lead and lead-bismuth) fast neutron systems, both critical and subcritical. Facilities, both under construction and those in operation are considered. It is expected that by providing the end users with detailed information on existing and future experimental facilities able to support innovative liquid metal cooled fast neutron systems, the publication will facilitate cooperation between organizations and knowledge transfer. An overview of the existing and future experimental facilities is presented in the body text of this publication. The profiles of all facilities in the form of individual papers are available on the attached CD-ROM and in the related on-line database maintained by the IAEA Catalogue of Facilities in Support of Liquid Metal-cooled Fast Neutron Systems (LMFNS Catalogue).
Liquid Metal Cooled Reactors
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201079077
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
Book Description
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.
Publisher:
ISBN: 9789201079077
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
Book Description
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.
Status of Fast Reactor Research and Technology Development
Author: International Atomic Energy Agency
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Structural Materials for Generation IV Nuclear Reactors
Author: Pascal Yvon
Publisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686
Book Description
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
Publisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686
Book Description
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
Structural Materials for Heavy Liquid Metal Cooled Fast Reactors
Author:
Publisher:
ISBN: 9781523149919
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
Book Description
"The compatibility of structural materials, such as steels with lead and lead-bismuth eutectic, poses a critical challenge in the development of heavy liquid metal (HLM) cooled fast reactors. Factors such as the high temperatures, fast neutron flux and irradiation exposure and corrosiveness provide a severe environment for the materials in these advanced reactor systems. The compatibility of liquid coolant with structural materials is critical for the development of innovative nuclear energy systems. To understand the current status of the research and development in this area as well as to provide a forum to exchange information on structural materials for HLM cooled reactors at the national and international levels, the IAEA organized a technical meeting. This resulted in the current publication which presents the summaries of the technical and the group sessions, conclusions and recommendations, and the papers presented at the event."--Publisher's description.
Publisher:
ISBN: 9781523149919
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
Book Description
"The compatibility of structural materials, such as steels with lead and lead-bismuth eutectic, poses a critical challenge in the development of heavy liquid metal (HLM) cooled fast reactors. Factors such as the high temperatures, fast neutron flux and irradiation exposure and corrosiveness provide a severe environment for the materials in these advanced reactor systems. The compatibility of liquid coolant with structural materials is critical for the development of innovative nuclear energy systems. To understand the current status of the research and development in this area as well as to provide a forum to exchange information on structural materials for HLM cooled reactors at the national and international levels, the IAEA organized a technical meeting. This resulted in the current publication which presents the summaries of the technical and the group sessions, conclusions and recommendations, and the papers presented at the event."--Publisher's description.
Challenges for Coolants in Fast Neutron Spectrum Systems
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201078209
Category :
Languages : en
Pages : 268
Book Description
This publication evaluates the different coolant options considered for nuclear applications with a fast neutron spectrum (i.e. fusion, fission and accelerators), compiles the latest information in the field and identifies research needs.
Publisher:
ISBN: 9789201078209
Category :
Languages : en
Pages : 268
Book Description
This publication evaluates the different coolant options considered for nuclear applications with a fast neutron spectrum (i.e. fusion, fission and accelerators), compiles the latest information in the field and identifies research needs.
Design Features and Operating Experience of Experimental Fast Reactors
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201364104
Category : Science
Languages : en
Pages : 0
Book Description
As a part of the IAEA efforts for knowledge preservation and data retrieval, this publication compiles and documents significant aspects of fast reactor engineering development and experience. Its focus is on research and development activities, experience with experimental facilities, and criteria for comparison liquid metal coolants.
Publisher:
ISBN: 9789201364104
Category : Science
Languages : en
Pages : 0
Book Description
As a part of the IAEA efforts for knowledge preservation and data retrieval, this publication compiles and documents significant aspects of fast reactor engineering development and experience. Its focus is on research and development activities, experience with experimental facilities, and criteria for comparison liquid metal coolants.
Handbook of Generation IV Nuclear Reactors
Author: Igor Pioro
Publisher: Woodhead Publishing
ISBN: 0128226536
Category : Technology & Engineering
Languages : en
Pages : 1112
Book Description
Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. - Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors - Includes new trends and developments since the first publication, as well as brand new case studies and appendices - Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Publisher: Woodhead Publishing
ISBN: 0128226536
Category : Technology & Engineering
Languages : en
Pages : 1112
Book Description
Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. - Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors - Includes new trends and developments since the first publication, as well as brand new case studies and appendices - Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
Author: Ferry Roelofs
Publisher: Woodhead Publishing
ISBN: 0081019815
Category : Science
Languages : en
Pages : 464
Book Description
Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. - Presents the latest information on one of the deliverables of the SESAME H2020 project - Provides an overview on the design and history of liquid metal cooled fast reactors worldwide - Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors - Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly - Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications
Publisher: Woodhead Publishing
ISBN: 0081019815
Category : Science
Languages : en
Pages : 464
Book Description
Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. - Presents the latest information on one of the deliverables of the SESAME H2020 project - Provides an overview on the design and history of liquid metal cooled fast reactors worldwide - Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors - Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly - Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications
Benchmark Analyses on the Natural Circulation Test Performed During the Phenix End-Of-Life Experiments: IAEA Tecdoc Series
Author: International Atomic Energy Agency
Publisher: International Atomic Energy Agency
ISBN: 9789201396105
Category : Political Science
Languages : en
Pages : 169
Book Description
"This publication is based on the experience of an IAEA coordinated research project on control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments. Presented in this publication are the benchmark analyses of the natural circulation test performed before the definite shutdown of the reactor. The experimental data gathered during these tests represent a unique resource to carry out validation analyses and code-to-code comparisons. The benchmark analyses allowed participants to investigate and verify several system and safety codes currently used in the analyses of liquid metal thermal hydraulics phenomena in sodium fast reactors."--Publisher's description.
Publisher: International Atomic Energy Agency
ISBN: 9789201396105
Category : Political Science
Languages : en
Pages : 169
Book Description
"This publication is based on the experience of an IAEA coordinated research project on control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments. Presented in this publication are the benchmark analyses of the natural circulation test performed before the definite shutdown of the reactor. The experimental data gathered during these tests represent a unique resource to carry out validation analyses and code-to-code comparisons. The benchmark analyses allowed participants to investigate and verify several system and safety codes currently used in the analyses of liquid metal thermal hydraulics phenomena in sodium fast reactors."--Publisher's description.