Design Features and Operating Experience of Experimental Fast Reactors

Design Features and Operating Experience of Experimental Fast Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2013

Total Pages: 0

ISBN-13: 9789201364104

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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.


Liquid Metal Cooled Reactors

Liquid Metal Cooled Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2007

Total Pages: 0

ISBN-13: 9789201079077

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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

Status of Fast Reactor Research and Technology Development

Author: International Atomic Energy Agency

Publisher:

Published: 2012

Total Pages: 0

ISBN-13: 9781523130191

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"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.


Molten Salt Reactors and Thorium Energy

Molten Salt Reactors and Thorium Energy

Author: Thomas James Dolan

Publisher: Elsevier

Published: 2024-01-25

Total Pages: 1068

ISBN-13: 0323993567

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Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. - A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts - Covers MSR applications, technical issues, reactor types and reactor designs - Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published - Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe


Structural Materials for Generation IV Nuclear Reactors

Structural Materials for Generation IV Nuclear Reactors

Author: Pascal Yvon

Publisher: Woodhead Publishing

Published: 2016-08-27

Total Pages: 686

ISBN-13: 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


Superphenix

Superphenix

Author: Joël Guidez

Publisher: Springer

Published: 2017-01-11

Total Pages: 372

ISBN-13: 9462392463

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For the first time a book has been written on the technological and scientific knowledge, acquired during, buiding , operation and even dismantling of the Superphenix plant. This reactor remains today the most powerful sodium fast breeder reactor operated in the world.(1200 MWe). The last fast breeder reactor operated in the world is BN 800 in Russia that reached his nominal power (800 MWe) in 2016. Joel Guidez began his career in the field of sodium-cooled fast reactors after leaving Ecole Centrale-Paris, in 1973. He has held various positions at Cadarache, Phenix and Superphenix, including as the head of the thermal hydraulic laboratory conducting tests for Phenix, Superphenix and the EFR European Fast Reactor project. He was also head of the OSIRIS research reactor, located at SACLAY, and of the HFR European Commission reactor, located in the Netherlands and spent two years as nuclear attaché at the French embassy in Berlin. His 2012 book “Phenix: the experience feedback” was translated into English and republished in 2013, and this new book on Superphenix is in the same spirit of thematic analysis of a reactor experience feedback. Gérard Prêle graduated from the Ecole Centrale-Lyon and entered EDF and the field of sodium-cooled fast reactors in 1983. In 1985 he joined Superphenix, where he was a duty engineer and was later in charge of safety. He has held various positions at Superphenix and Phenix and was a fast neutron reactor (SFR) engineer at the EDF Centre Lyonnais d’Ingénierie (CLI). He worked as Safety Security Environment and Radiation Protection Mission head in Superphenix at the beginning of dismantling and then in the field of PWR for two years. Since 2006 he has been involved in the Gen IV and the SFR/Astrid projects. Today, as an SFR/system and operations expert, one of his major roles is assisting the CEA in the preliminary design of the ASTRID reactor.


Knowledge Management and Its Implementation in Nuclear Organizations

Knowledge Management and Its Implementation in Nuclear Organizations

Author: International Atomic Energy Agency

Publisher: IAEA Nuclear Energy Series No.

Published: 2016

Total Pages: 0

ISBN-13: 9789201072153

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The IAEA's nuclear knowledge management activities provide guidance in knowledge management and assist in transferring and preserving knowledge, exchanging information, establishing and supporting cooperative networks and in training the next generation of nuclear experts. This publication shares best practices and experiences based on the knowledge management assist visit programme undertaken by IAEA expert teams during the period 2005-2013. These visits have involved different types of organizations, including nuclear power plants, nuclear R&D organizations and nuclear based educational establishments such as universities. Based on the records of these visits, a secondary aim of this publication is to provide feedback and recommendations for future development of the assessment tool(s) and participating organizations for improving future assistance.


Benchmark Analyses on the Natural Circulation Test Performed During the Phenix End-Of-Life Experiments: IAEA Tecdoc Series

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

Published: 2013-07-01

Total Pages: 169

ISBN-13: 9789201396105

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"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.