Download or read book Fast Reactor Safety written by John Graham and published by Elsevier. This book was released on 2012-12-02 with total page 390 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Fast Reactor Fuel Type and Reactor Safety Performance written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Fast Reactors written by Joel Guidez and published by Academic Press. This book was released on 2022-09-21 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Download or read book Reactor Safety written by and published by . This book was released on 1971 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the 1990 International Fast Reactor Safety Meeting written by and published by . This book was released on 1990 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics and Fuel Performance of Reactor Based Plutonium Disposition written by and published by OECD Publishing. This book was released on 1999 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Summary of APDA Fast Reactor Safety Studies written by W. H. Jens and published by . This book was released on 1956 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the International Meeting on Fast Reactor Safety Technology Seattle Washington August 1923 1979 written by and published by . This book was released on 1979 with total page 532 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Power Reactor Safety written by Elmer Eugene Lewis and published by John Wiley & Sons. This book was released on 1977 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor and Fuel processing Technology written by and published by . This book was released on 1968 with total page 654 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Reactor Safety written by Frank Reginald Farmer and published by . This book was released on 1977 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides up-to-date information on a wide variety of places around the globe. Provides access to place-based web sites.
Download or read book Fundamental Aspects of Nuclear Reactor Fuel Elements written by Donald R. Olander and published by . This book was released on 1976 with total page 628 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fast Reactor Safety written by and published by . This book was released on 1960-12 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the International Meeting on Fast Reactor Safety and Related Physics October 5 8 1976 Chicago Illinois Accident analysis structural dynamics written by and published by . This book was released on 1977 with total page 596 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the International Meeting on Fast Reactor Safety and Related Physics October 5 8 1976 Chicago Illinois Phenomenology written by and published by . This book was released on 1977 with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Safety Issues Associated with Plutonium Involvement in the Nuclear Fuel Cycle written by Theodore A. Parish and published by Springer Science & Business Media. This book was released on 1999-02-28 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt: The "VOLGA" conferences, hosted in odd-numbered years by the Department of Theoretical and Experimental Reactor Physics of the Moscow Engineering Physics Institute (MEPhI), are some of the most prestigious technical meetings held in Russia. Traditionally, these conferences present the opportunity for reactor physicists from around the world to gather at MEPhI's holiday camp on the banks of the Volga river (near Tver) to exchange ideas and explore innovative concepts related to nuclear power development. In 1997, NATO became involved in the "VOLGA" meetings for the first time by co-sponsoring "VOLGA97" as an advanced research workshop. This workshop broke with tradition a bit in that the venue was moved from MEPhI's holiday camp to a location nearer Moscow. The workshop program was effectively organized in order to cover a broad range of topics relating to the theme of the meeting. Generally, the papers concerned safety related questions associated with utilizing both weapons-grade and reactor-grade plutonium in the nuclear fuel cycle, including facility requirements, licensing issues, proliferation risks, and a variety of advanced concepts for alternative fuel cycles. The program contained a total of ninety-nine papers presented in five days of sessions.
Download or read book Innovative Design of Uranium Startup Fast Reactors written by Tingzhou Fei and published by . This book was released on 2012 with total page 283 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
