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The Integral Fast Reactor (IFR) is an innovative liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. The design features that together fulfill these goals are: (1) a liquid metal (sodium) coolant, (2) a pool-type reactor primary system configuration, (3) an advanced ternary alloy metallic fuel, and (4) an integral fuel cycle. This paper reviews the design features that contribute to the safety margins inherent to the IFR concept. Special emphasis is placed on the ability of the IFR design to accommodate anticipated transients without scram (ATWS).
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The Integral Fast Reactor (IFR) concept is an innovative approach to liquid metal reactor design which is being studied by Argonne National Laboratory. Two of the key features of the IFR design are a metal fuel core design, based on the fuel technology developed at EBR-II, and an integral fuel cycle with a colocated fuel cycle facility based on the compact and simplified process steps made possible by the use of metal fuel. The paper presents the safety characteristics of the IFR concept which derive from the use of metal fuel. Liquid metal reactors, because of the low pressure coolant operating far below its boiling point, the natural circulation capability, and high system heat capacities, possess a high degree of inherent safety. The use of metallic fuel allows the reactor designer to further enhance the system capability for passive accommodation of postulated accidents.
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Key features of the IFR consist of a pool-type plant arrangement, a metal fuel-based core design, and an integral fuel cycle with colocated fuel cycle facility. Both the basic concept and the technology base have been demonstrated through actual integral cycle operation in EBR-II. This paper discusses the inherent safety characteristics of the IFR concept. (DLC).
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The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents.
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The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that fully exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes key features and potential advantages of the IFR concept, technology development status, fuel cycle economics potential, and future development path.
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The IFR concept employs a pool layout, a U/Pu/Zr metal alloy fuel and a closed fuel cycle based on pyrometallurgical reprocessing and injection casting refabrication. The reactor physics issues of designing for inherent safety and for a closed fissile self-sufficient integral fuel cycle with uranium startup and potential actinide transmutation are discussed.
Author: John Graham
Publisher: Elsevier
ISBN: 0323152651
Category : Technology & Engineering
Languages : en
Pages : 390
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Fast Reactor Safety deals with safety design criteria and methodology for fast reactors. Topics covered include safety evaluation methods, system disturbances, containment, and licensing. The characteristics of fast reactors, including heat ratings and coolants, are also discussed. Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors, gas-cooled fast breeder reactors, and steam-cooled fast breeder reactors. The next chapter looks at safety criteria that are set to define the design of a safe plant, together with the safety features that might be included. The remaining chapters focus on the particular problems of a sodium-cooled design; containment building and primary circuit and vessel containment; and licensing of the plant. This monograph is intended for graduates and undergraduates in nuclear engineering who are attending courses in reactor safety.
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Languages : en
Pages : 54
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The results of a preliminary assessment of the safety characteristics of the integral fast reactor concept are presented. The response of metal fueled cores to a variety of transients are examined. The range of events that were assessed include transient overpower (TOP) without scram, loss-of-flow (LOF) without scram, local fuel failure events, and core melt accidents. The results show that by taking advantage of the inherent characteristics of a pool plant and metallic cores, a plant design can be developed that does not require the action of active safety systems to prevent significant damage to the core for any single off-normal occurrence. Further, even in the case of multiple failures, significant times are available for corrective action.
Author: Jeffery Lewins
Publisher: Springer Science & Business Media
ISBN: 1461399254
Category : Science
Languages : en
Pages : 239
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Book Description
The editors are happy to present the twentieth volume in the review series Advances in Nuclear Science and Technology. Lahey and Drew, our first authors, present a concise development of the equations for two-phase flow, essential to the understanding of normal and, even more, accidental behavior in water-cooled reactors. The commitment to the PWR in Europe (now joined by England in this respect) and the aftermath of Chernobyl in the U.S.S.R. put continuing emphasis on the need for good understanding of two-phase phenomena to provide good modelling. The second review, by Downar and Sesonske, of light water reactor fuel modelling, follows this LWR interest and emphasises a current major economic interest: how to get the most out of fuel. Recollecting that the capital cost of nuclear power is high, it is easy to overlook the fact that in the lifetime of a plant as much money is spent on fuel as capital. Optimization is worthwhile. The U.S. scene still does not practice recycling whereas the European scene does. Now that the United Kingdom is building its first (commercial) light water reactor, the linear modelling of burnup exploited by the second authors will prove even more useful, although previously exploited for advanced gas-cooled reactors. If the U.K. is behind in this respect, the recycling undertaken by France and England has led to trial use of plutonium in thermal reactors but, even more, the availability of plutonium for fast reactors.
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The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab.
