Koch, former manager of the Experimental Breeder Reactor-II (EBR-II), offers a first-hand account of the development, design, construction, and initial operation of this facility, which has contributed to the foundation of knowledge for all fast reactors. He explains why certain design choices were made while others were rejected. He also outlines how he thinks that future sodium cooled fast reactors should be designed, based on the experience gained with EBR-II. An appendix traces the lineage of EBR-II, including original memos and meeting notes, beginning with Enrico Fermi and Walter Zinn and progressing to the formation of the EBR-II project. B&w photos and illustrations are included. The book is of interest to designers of future fast reactors. There is no subject index.
In this comprehensive volume, Stevenson recounts the history of the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF), and the process requirements of this unique technology. The author also explains the reasons behind the remarkable success of both the EBR-II and the FCF. These data, presented as a useful information source, should be of considerable significance to the continuing development of nuclear power.
The initial "Hazard Summary Report - Experimental Breeder Reactor-II (EBR-II)" was published as ANL-5719 in May, 1957. At the time of preparation of ANL-5719 (early 1957), the design of the EBR-II Facility was in progress - construction had not started. This Addendum is limited, for the most part, to changes which have been made in the EBR-II Facility, and to supporting experimental data developed, since the publication of ANL-5719.
"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.
This book provides a readable and thought-provoking analysis of the issues surrounding nuclear fuel reprocessing and fast-neutron reactors, including discussion of resources, economics, radiological risk and resistance to nuclear proliferation. It describes the history and science behind reprocessing, and gives an overview of the status of reprocessing programmes around the world. It concludes that such programs should be discontinued. While nuclear power is seen by many as the only realistic solution to the carbon emission problem, some national nuclear establishments have been pursuing development and deployment of sodium-cooled plutonium breeder reactors, and plutonium recycling. Its proponents argue that this system would offer significant advantages relative to current light water reactor technology in terms of greater uranium utilization efficiency, and that separating out the long-lived plutonium and other transuranics from spent fuel and fissioning them in fast reactors would greatly reduce the duration of the toxicity of radioactive waste. However, the history of efforts to deploy this system commercially in a number of countries over the last six decades has been one of economic and technical failure and, in some cases, was used to mask clandestine nuclear weapon development programs. Covering topics of significant public interest including nuclear safety, fuel storage, environmental impact and the spectre of nuclear terrorism, this book presents a comprehensive analysis of the issue for nuclear engineers, policy analysts, government officials and the general public. "Frank von Hippel, Jungmin Kang, and Masafumi Takubo, three internationally renowned nuclear experts, have done a valuable service to the global community in putting together this book, which both historically and comprehensively covers the “plutonium age” as we know it today. They articulate in a succinct and clear manner their views on the dangers of a plutonium economy and advocate a ban on the separation of plutonium for use in the civilian fuel cycle in view of the high proliferation and nuclear-security risks and lack of economic justification." (Mohamed ElBaradei, Director General, International Atomic Energy Agency (1997-2009), Nobel Peace Prize (2005)) "The 1960s dream of a ‘plutonium economy’ has not delivered abundant low-cost energy, but instead has left the world a radioactive legacy of nuclear weapons proliferation and the real potential for nuclear terrorism. Kang, Takubo, and von Hippel explain with power and clarity what can be done to reduce these dangers. The governments of the remaining countries whose nuclear research and development establishments are still pursuing the plutonium dream should pay attention.” (Senator Edward Markey, a leader in the US nuclear-disarmament movement as a member of Congress since 1976) "The authors have done an invaluable service by putting together in one place the most coherent analysis of the risks associated with plutonium, and the most compelling argument for ending the practice of separating plutonium from spent fuel for any purpose. They have given us an easily accessible history of the evolution of thinking about the nuclear fuel cycle, the current realities of nuclear power around the world and, arguably most important, a clear alternative path to deal with the spent fuel arising from nuclear reactors for decades to centuries to come." (Robert Gallucci, Chief US negotiator with North Korea (1994); Dean, Georgetown University School of Foreign Service (1996-2009); President, MacArthur Foundation (2009-2014))
The Integral Fast Reactor (IFR) is a fast reactor system developed at Argonne National Laboratory in the decade 1984 to 1994. The IFR project developed the technology for a complete system; the reactor, the entire fuel cycle and the waste management technologies were all included in the development program. The reactor concept had important features and characteristics that were completely new and fuel cycle and waste management technologies that were entirely new developments. The reactor is a "fast" reactor - that is, the chain reaction is maintained by "fast" neutrons with high energy - which produces its own fuel. The IFR reactor and associated fuel cycle is a closed system. Electrical power is generated, new fissile fuel is produced to replace the fuel burned, its used fuel is processed for recycling by pyroprocessing - a new development - and waste is put in final form for disposal. All this is done on one self-sufficient site.The scale and duration of the project and its funding made it the largest nuclear energy R and D program of its day. Its purpose was the development of a long term massive new energy source, capable of meeting the nation's electrical energy needs in any amount, and for as long as it is needed, forever, if necessary. Safety, non-proliferation and waste toxicity properties were improved as well, these three the characteristics most commonly cited in opposition to nuclear power.Development proceeded from success to success. Most of the development had been done when the program was abruptly cancelled by the newly elected Clinton Administration. In his 1994 State of the Union address the president stated that "unnecessary programs in advanced reactor development will be terminated." The IFR was that program.This book gives the real story of the IFR, written by the two nuclear scientists who were most deeply involved in its conception, the development of its R and D program, and its management.Between the scientific and engineering papers and reports, and books on the IFR, and the non-technical and often impassioned dialogue that continues to this day on fast reactor technology, we felt there is room for a volume that, while accurate technically, is written in a manner accessible to the non-specialist and even to the non-technical reader who simply wants to know what this technology is.
A description of the EBR-II shield and the methods employed in arriving at the final design are presented. The major shield design problems for that reactor are enumerated and discussed.
The EBR-II reactor consists of an enriched core surrounded on all sides by a fertile blanket of depleted uranium. The fuel elements which comprise the core section of the reactor consist of small diameter cylindrical pin assemblies. The design of the fuel element is influenced by the desire for high thermal performance, high burnup, and simplicity of construction. The fuel pin is a loss fit in a thin-walled tube which provides a clearance annulus between the pin and the tube wall. This annulus is filled with static sodium to provide a heat transfer bond between the fuel and fuel tube. Heat is removed from the fuel element by the primary sodium flowing along the outside of the fuel tube.
