Download or read book Decommissioning of Sodium Cooled Fast Reactors written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Operational and Decommissioning Experience with Fast Reactors written by and published by . This book was released on 2004 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt: Operational experience constitutes an important aspect of any fast reactor knowledge base. It is within this context that the IAEA convened a Topical Technical Meeting on Feedback from Operational and Decommissioning Experience with Fast Reactors. This publication presents the proceedings of this meeting.
Download or read book Decommissioning of Fast Reactors After Sodium Draining written by International Atomic Energy Agency and published by . This book was released on 2009 with total page 175 pages. Available in PDF, EPUB and Kindle. Book excerpt: Decommissioning of fast reactors and other sodium bearing facilities is a domain in which considerable experience has been accumulated. This publication arises from an IAEA technical meeting convened to address decommissioning experience with fast reactors, in particular with regard to the decommissioning of components after sodium draining. Experience gained from the decommissioning of both active sodium loops and sodium cooled fast reactors was reviewed and analysed. The publication presents information on decommissioning and treatment process development, reactor and facility decommissioning experimental feedback, sodium cooled fast reactor waste characterization and treatment, and reactor decommissioning strategy.
Download or read book Sodium Fast Reactors with Closed Fuel Cycle written by Baldev Raj and published by CRC Press. This book was released on 2015-04-15 with total page 901 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book:Offers in-depth coverage of reactor physics, materials, design, s
Download or read book Sodium cooled Nuclear Reactors written by Jean-François Parisot and published by . This book was released on 2016 with total page 232 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Optimisation of Sodium cooled Fast Reactors written by Joyce S. Davis and published by Thomas Telford Publishing. This book was released on 1978 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Status of Fast Reactor Research and Technology Development written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "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.
Download or read book Treatment of Residual Sodium and Sodium Potassium from Fast Reactors written by International Atomic Energy Agency and published by IAEA Tecdoc. This book was released on 2015 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication covers a range of topics related to removal of residual radioactive sodium and sodium potassium coolant from reactor vessels and components in connection with decommissioning of liquid metal cooled reactors. The testing and application of relevant key technologies in five countries at a number of facilities are described. The technologies include passivation of the residuals, methods to control and monitor the processes, and also gaining access to locations that are difficult to reach and where residual sodium may be found. Non-radioactive sodium waste is not specifically considered in this publication. However, the approach, procedures, and recommendations that apply to safe management of radioactive sodium waste are also largely applicable to non-radioactive sodium. In addition to the technical topics, lessons learned for management of removal and disposal of residual sodium and sodium potassium are also presented.
Download or read book Sodium cooled Fast Reactors written by Masaki Morishita and published by Academic Press. This book was released on 2022-07-22 with total page 666 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sodium-cooled Fast Reactors is the third volume in the JSME Series on Thermal and Nuclear Power Generation, which presents a comprehensive view of the latest research and activities from around the globe. Volume Editors Masaki Morishita and Hiroyuki Ohshima, along with their team of expert contributors, combine their knowledge and experience to provide a solid understanding of the history of SFRs and work carried out in Japan to date. This book uniquely includes case studies from these global regions to highlight SFR uses, benefits and challenges, focusing on their safety, design, operation, and maintenance. Unique to this publication, the JSME cover key technological advances which will shape power generation of the future, including developments in the use of AI for design. Drawing on their unique experience, the authors pass on lessons learned and best practices to support professionals and researchers in their development and design of this advanced reactor type. 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 mainly from Japan 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 SFR systems
Download or read book Dynamic Simulation of Sodium Cooled Fast Reactors written by G Vaidyanathan and published by CRC Press. This book was released on 2022-11-18 with total page 289 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor. The book • Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium. • Compares different numerical techniques and brings out the best one for the solution of the models. • Provides a methodology of validation based on experiments. • Examines modeling and simulation aspects necessary for the safe design of a fast reactor. • Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems. • Discusses the application of the models to the design of a sodium-cooled fast reactor It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.
Download or read book Decommissioning of Experimental Breeder Reactor II Complex Post Sodium Draining written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Experimental Breeder Reactor - II (EBR-II) was shutdown in September 1994 as mandated by the United States Department of Energy. This sodium-cooled reactor had been in service since 1964. The bulk sodium was drained from the primary and secondary systems and processed. Residual sodium remaining in the systems after draining was converted into sodium bicarbonate using humid carbon dioxide. This technique was tested at Argonne National Laboratory in Illinois under controlled conditions, then demonstrated on a larger scale by treating residual sodium within the EBR-II secondary cooling system, followed by the primary tank. This process, terminated in 2002, was used to place a layer of sodium bicarbonate over all exposed surfaces of sodium. Treatment of the remaining EBR-II sodium is governed by the Resource Conservation and Recovery Act (RCRA). The Idaho Department of Environmental Quality issued a RCRA Operating Permit in 2002, mandating that all hazardous materials be removed from EBR-II within a 10 year period, with the ability to extend the permit and treatment period for another 10 years. A preliminary plan has been formulated to remove the remaining sodium and NaK from the primary and secondary systems using moist carbon dioxide, steam and nitrogen, and a water flush. The moist carbon dioxide treatment was resumed in May 2004. As of August 2005, approximately 60% of the residual sodium within the EBR-II primary tank had been treated. This process will continue through the end of 2005, when it is forecast that the process will become increasingly ineffective. At that time, subsequent treatment processes will be planned and initiated. It should be noted that the processes and anticipated costs associated with these processes are preliminary. Detailed engineering has not been performed, and approval for these methods has not been obtained from the regulator or the sponsors.
Download or read book Decommissioning of Nuclear Facilities written by OECD Nuclear Energy Agency and published by Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; Washington, D.C. : OECD Publications and Information Centre. This book was released on 1991 with total page 142 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Liquid Metal Cooled Reactors written by International Atomic Energy Agency and published by . This book was released on 2007 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Superphenix written by Joël Guidez and published by Springer. This book was released on 2017-01-11 with total page 372 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Concept for Dismantling the Reactor Vessel and the Biological Shield of the Compact Sodium Cooled Nuclear Reactor Facility KNK written by and published by . This book was released on 2002 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Compact Sodium-cooled Nuclear Reactor Facility (KNK) was an experimental nuclear power plant of 20 MW electric power erected on the premises of the Karlsruhe Research Center. The plant was initially run as KNK I with a thermal core between 1971 and 1974 and then, between 1977 and 1991, with a fast core as the KNK II fast breeder plant. Under the decommissioning concept, the plant is to be decommissioned completely to green field conditions at the end of 2005 in ten steps, i.e. under the corresponding ten decommissioning permits. To this day, nine decommissioning permits have been issued, the first one in 1993 and the most recent one, number nine, in 2001. The decommissioning and demolition activities covered by decommissioning permits 1 to 7 have been completed. Under the 8th Decommissioning Permit, the components of the primary system and the rotating reactor top shield are to be removed by late 2001. Under the 9th Decommissioning Permit, the reactor vessel with its internals, the primary shield, and the biological shield are to be dismantled. The residual sodium volume in the reactor vessel was estimated to amount to approx. 30 l. The maximum Co-60 activation is on the order of 107-108 Bq/g; the maximum dose rate in the middle of the vessel was measured in April 1997 to be 55 Sv/h. The difficulty involved especially in dismantling KNK, on the one hand, is posed by the residual sodium in the plant, which determines the choice of neither wet nor thermical techniques to be used in disassembly. Another difficulty is caused by the depth of activation by fast neutrons, as a result of which not only the reactor vessel proper, but also the entire primary shield (60 cm of grey cast iron) and large parts of the biological shield must be disassembled and disposed of under remote control.
Download or read book Application of the Technology Neutral Framework to Sodium Cooled Fast Reactors written by Brian Carl Johnson and published by . This book was released on 2010 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sodium cooled fast reactors (SFRs) are considered as a novel example to exercise the Technology Neutral Framework (TNF) proposed in NUREG- 1860. One reason for considering SFRs is that they have historically had a licensing problem due to postulated core disruptive accidents. Two SFR designs are considered, and both meet the goals of the TNF that LWRs typically would not. Considering these goals have been met, a method for improving economics is proposed where systems of low risk-importance are identified as candidates for removal, simplification, or removal from safety grade. Seismic risk dominates these designs and is found to be a limiting factor when applying the TNF. The contributions of this thesis are the following: 1. Functional event trees are developed as a tool to allow different designs to be compared on an equal basis. Functional event trees are useful within the TNF as a method for the selection of Licensing Basis Events (LBEs) which take the place of traditional Design Basis Accidents. 2. A new importance measure, Limit Exceedance Factor (LEF), is introduced that measures the margin in system failure probability. It can be used directly with the TNF where standard importance measures cannot. It also reveals that some systems that appear to be of high risk-importance with standard importance measures may have significant margin. 3. The seismic risk dominates these designs. It is shown that even under optimistic assumptions, the goals of the TNF cannot be met by a typical reactor. The effect of seismic isolation to reduce the frequency of seismically initiated large releases is also analyzed and found to be insufficient to reach the goals of the TNF. A limit on initiating event frequency that is consistent with current practices is proposed.
Download or read book Handbook of Generation IV Nuclear Reactors written by Igor Pioro and published by Woodhead Publishing. This book was released on 2022-12-07 with total page 1112 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
