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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Fast Reactor Fuel Type and Reactor Safety Performance R. Wigeland, Idaho National Laboratory J. Cahalan, Argonne National Laboratory The sodium-cooled fast neutron reactor is currently being evaluated for the efficient transmutation of the highly-hazardous, long-lived, transuranic elements that are present in spent nuclear fuel. One of the fundamental choices that will be made is the selection of the fuel type for the fast reactor, whether oxide, metal, carbide, nitride, etc. It is likely that a decision on the fuel type will need to be made before many of the related technologies and facilities can be selected, from fuel fabrication to spent fuel reprocessing. A decision on fuel type should consider all impacts on the fast reactor system, including safety. Past work has demonstrated that the choice of fuel type may have a significant impact on the severity of consequences arising from accidents, especially for severe accidents of low probability. In this paper, the response of sodium-cooled fast reactors is discussed for both oxide and metal fuel types, highlighting the similarities and differences in reactor response and accident consequences. Any fast reactor facility must be designed to be able to successfully prevent, mitigate, or accommodate all consequences of potential events, including accidents. This is typically accomplished by using multiple barriers to the release of radiation, including the cladding on the fuel, the intact primary cooling system, and most visibly the reactor containment building. More recently, this has also included the use of 'inherent safety' concepts to reduce or eliminate the potential for serious damage in some cases. Past experience with oxide and metal fuel has demonstrated that both fuel types are suitable for use as fuel in a sodium-cooled fast reactor. However, safety analyses for these two fuel types have also shown that there can be substantial differences in accident consequences due to the neutronic and thermophysical properties of the fuel and their compatibility with the reactor coolant, with corresponding differences in the challenges presented to the reactor developers. Accident phenomena are discussed for the sodium-cooled fast reactor based on the mechanistic progression of conditions from accident initiation to accident termination, whether a benign state is achieved or more severe consequences are expected. General principles connecting accident phenomena and fuel properties are developed from the oxide and metal fuel safety analyses, providing guidelines that can be used as part of the evaluation for selection of fuel type for the sodium-cooled fast reactor.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Fast Reactor Fuel Type and Reactor Safety Performance R. Wigeland, Idaho National Laboratory J. Cahalan, Argonne National Laboratory The sodium-cooled fast neutron reactor is currently being evaluated for the efficient transmutation of the highly-hazardous, long-lived, transuranic elements that are present in spent nuclear fuel. One of the fundamental choices that will be made is the selection of the fuel type for the fast reactor, whether oxide, metal, carbide, nitride, etc. It is likely that a decision on the fuel type will need to be made before many of the related technologies and facilities can be selected, from fuel fabrication to spent fuel reprocessing. A decision on fuel type should consider all impacts on the fast reactor system, including safety. Past work has demonstrated that the choice of fuel type may have a significant impact on the severity of consequences arising from accidents, especially for severe accidents of low probability. In this paper, the response of sodium-cooled fast reactors is discussed for both oxide and metal fuel types, highlighting the similarities and differences in reactor response and accident consequences. Any fast reactor facility must be designed to be able to successfully prevent, mitigate, or accommodate all consequences of potential events, including accidents. This is typically accomplished by using multiple barriers to the release of radiation, including the cladding on the fuel, the intact primary cooling system, and most visibly the reactor containment building. More recently, this has also included the use of 'inherent safety' concepts to reduce or eliminate the potential for serious damage in some cases. Past experience with oxide and metal fuel has demonstrated that both fuel types are suitable for use as fuel in a sodium-cooled fast reactor. However, safety analyses for these two fuel types have also shown that there can be substantial differences in accident consequences due to the neutronic and thermophysical properties of the fuel and their compatibility with the reactor coolant, with corresponding differences in the challenges presented to the reactor developers. Accident phenomena are discussed for the sodium-cooled fast reactor based on the mechanistic progression of conditions from accident initiation to accident termination, whether a benign state is achieved or more severe consequences are expected. General principles connecting accident phenomena and fuel properties are developed from the oxide and metal fuel safety analyses, providing guidelines that can be used as part of the evaluation for selection of fuel type for the sodium-cooled fast reactor.
Author: John Graham Publisher: Elsevier ISBN: 0323152651 Category : Technology & Engineering Languages : en Pages : 390
Book Description
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.
Author: Joel Guidez Publisher: Academic Press ISBN: 0128219424 Category : Science Languages : en Pages : 228
Book Description
Fast Reactors: A Solution to Fight Against Global Warming presents the current status of fast-reactor nuclear generation technology, with a focus on ecology and sustainability benefits for the future. Author Joel Guidez analyzes past failures and limited deployment reasons to help drive this power generation method forward to a cleaner and more sustainable energy environment. The book covers safety aspects, short-life waste management, multirecycling, and biodiversity preservation to provide a well-rounded reference on the topic. Analyzes reasons for past failures and presents the advantages of fast reactors Reviews the status of fast-reactor technology, for sodium fast reactors and molten salt reactors with liquid fuel Presents ways in which fast nuclear reactors can help fight climate change and promote sustainability for the future
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.
Author: Willem Frederik Geert van Rooijen Publisher: IOS Press ISBN: 9781586036966 Category : Technology & Engineering Languages : en Pages : 160
Book Description
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Author: Tingzhou Fei Publisher: ISBN: Category : Languages : en Pages : 283
Book Description
Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic fuels from reprocessing facilities, which are not available in the U.S. Thus, deployment of fast reactors requires decoupling from reprocessing facilities. This motivates the design and deployment of Uranium Startup sodium Fast Reactors (USFR) on a once-through fuel cycle in order to facilitate the transition to fast reactors by reducing their plant costs and increase capacity factor. Three different fuel types including uranium carbide (UC), metal (UZr) and uranium oxide (UO2) are investigated and analyzed using the ERANOS code for potential use in USFR designs. A key enabling factor is use of high-albedo MgO or Zr reflectors in place of fertile blankets to reduce uranium enrichment and improve non-proliferation resistance. The different compositions in different fuel types result in different neutronic performance. The softer spectrum and lower allowable fuel volume fractions of oxide fuel have shorter fuel cycle length due to reactivity constraints, whereas fast neutron fluence plays an important role in determining the fuel cycle length in metal cores due to the harder spectrum. Moderators are deliberately added in the metal fuels to lower the fast neutron fluence. Carbide cores have a slightly harder neutron spectrum than oxide cores and a larger achievable fuel volume fraction. USFRs using all three fuel types (UC, U0 2 and UZr) have lower fuel cycle cost (6.27, 6.09 and 5.77mills/kWhe) and comparable uranium consumption (0.50, 0.55, and 0.53kgNatU/MWde) compared with typical LWRs (6.39nills/kWhe and 0.53kgNatU/MWde). All USFR designs have maximum neutron fluence below 5E23n/cm2. All three USFR designs have pressure drop below 0.7MPa and maximum temperature below the limit for each fuel type. Both carbide and metal fuel have excellent passive safety performance. It is concluded that the USFR approach is a competitive way to accelerate fast reactor development.
Author: Tetsuaki Takeda Publisher: Academic Press ISBN: 012821032X Category : Business & Economics Languages : en Pages : 478
Book Description
High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. 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 from Japan, the US and Europe 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 HTGR systems.
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Author: John Graham
Author: Joel Guidez
Author: International Atomic Energy Agency
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Author: Willem Frederik Geert van Rooijen
Author: K. R. Kummerer
Author: Tingzhou Fei
Author: Tetsuaki Takeda