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Review Of Reactor Safety Analyses Of Fast And Liquid Metal Cooled Reactors
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Book Synopsis Review of Reactor Safety Analyses of Fast and Liquid Metal Cooled Reactors by : R. E. Shaver
Download or read book Review of Reactor Safety Analyses of Fast and Liquid Metal Cooled Reactors written by R. E. Shaver and published by . This book was released on 1967 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Small Liquid Metal Cooled Reactor Safety Study by : N. Brown
Download or read book Small Liquid Metal Cooled Reactor Safety Study written by N. Brown and published by . This book was released on 2005 with total page 63 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Small Liquid Metal Cooled Reactor Safety Study documents results from activities conducted under Small Liquid Metal Fast Reactor Coordination Program (SLMFR-CP) Agreement, January 2004, between the Central Research Institute of the Electric Power Industry (CRIEPI) of Japan and the Lawrence Livermore National Laboratory (LLNL)[1]. Evaluations were completed on topics that are important to the safety of small sodium cooled and lead alloy cooled reactors. CRIEPI investigated approaches for evaluating postulated severe accidents using the CANIS computer code. The methods being developed are improvements on codes such as SAS 4A used in the US to analyze sodium cooled reactors and they depend on calibration using safety testing of metal fuel that has been completed in the TREAT facility. The 4S and the small lead cooled reactors in the US are being designed to preclude core disruption from all mechanistic scenarios, including selected unprotected transients. However, postulated core disruption is being evaluated to support the risk analysis. Argonne National Laboratory and the University of California Berkeley also supported LLNL with evaluation of cores with small positive void worth and core designs that would limit void worth. Assessments were also completed for lead cooled reactors in the following areas: (1) continuing operations with cladding failure, (2) large bubbles passing through the core and (3) recommendations concerning reflector control. The design approach used in the US emphasizes reducing the reactivity in the control mechanisms with core designs that have essentially no, or a very small, reactivity change over the core life. This leads to some positive void worth in the core that is not considered to be safety problem because of the inability to identify scenarios that would lead to voiding of lead. It is also believed that the void worth will not dominate the severe accident analysis. The approach used by 4S requires negative void worth throughout the core life, which leads to large reactivity worth in the control systems. The conclusions from the evaluations support the high level of safety that can be achieved with small liquid metal cooled reactors using either approach.
Book Synopsis Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors by : Ferry Roelofs
Download or read book Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors written by Ferry Roelofs and published by Woodhead Publishing. This book was released on 2018-11-30 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. Presents the latest information on one of the deliverables of the SESAME H2020 project Provides an overview on the design and history of liquid metal cooled fast reactors worldwide Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications
Book Synopsis Safety of Sodium-Cooled Fast Reactors by : Songbai Cheng
Download or read book Safety of Sodium-Cooled Fast Reactors written by Songbai Cheng and published by Springer Nature. This book was released on 2021-09-27 with total page 313 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book highlights the advances and trends in the safety analysis of sodium-cooled fast reactors, especially from the perspective of particle bed-related phenomena during core disruptive accidents. A sodium-cooled fast reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems. Its safety is a critical issue during its R&D process. The book elaborates on research progresses in particle bed-related phenomena in terms of the molten-pool mobility, the molten-pool sloshing motion, the debris bed formation behavior, and the debris bed self-leveling behavior. The book serves as a good reference for researchers, professionals, and postgraduate students interested in sodium-cooled fast reactors. Knowledge provided is also useful for those who are engaging in severe accident analysis for lead-cooled fast reactors and light water reactors.
Book Synopsis Fast Reactor Safety by : John Graham
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.
Book Synopsis Safety Problems of Liquid-metal-cooled Fast Breeder Reactors by : C. N. Kelber
Download or read book Safety Problems of Liquid-metal-cooled Fast Breeder Reactors written by C. N. Kelber and published by . This book was released on 1970 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Review of the Current Status of Research on the Chemical and Physical Aspects of Liquid-metal-cooled Fast Breeder Reactor Safety by : A. W. Castleman
Download or read book A Review of the Current Status of Research on the Chemical and Physical Aspects of Liquid-metal-cooled Fast Breeder Reactor Safety written by A. W. Castleman and published by . This book was released on 1970 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Liquid Metal Cooled Reactors by : International Atomic Energy Agency
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.
Author :United States. Congress. Joint Committee on Atomic Energy. Ad Hoc Subcommittee to Review the Liquid Metal Fast Breeder Reactor Program Publisher : ISBN 13 : Total Pages :620 pages Book Rating :4.:/5 ( download)
Book Synopsis Review of the Liquid Metal Fast Breeder Program by : United States. Congress. Joint Committee on Atomic Energy. Ad Hoc Subcommittee to Review the Liquid Metal Fast Breeder Reactor Program
Download or read book Review of the Liquid Metal Fast Breeder Program written by United States. Congress. Joint Committee on Atomic Energy. Ad Hoc Subcommittee to Review the Liquid Metal Fast Breeder Reactor Program and published by . This book was released on 1975 with total page 620 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book LMFBR Safety written by J. R. Buchanan and published by . This book was released on 1976 with total page 548 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Symposium on the Thermal and Hydraulic Aspects of Nuclear Reactor Safety: Liquid metal fast breeder reactors by : Owen C. Jones
Download or read book Symposium on the Thermal and Hydraulic Aspects of Nuclear Reactor Safety: Liquid metal fast breeder reactors written by Owen C. Jones and published by . This book was released on 1977 with total page 348 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Safety written by and published by . This book was released on 1975 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 TID. written by and published by . This book was released on 19?? with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Safety and Core Design of Large Liquid-metal Cooled Fast Breeder Reactors by : Staffan Alexander Qvist
Download or read book Safety and Core Design of Large Liquid-metal Cooled Fast Breeder Reactors written by Staffan Alexander Qvist and published by . This book was released on 2013 with total page 650 pages. Available in PDF, EPUB and Kindle. Book excerpt: In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions from human activities, the world is in ever more desperate need of new, inexhaustible, safe and clean primary energy sources. A viable solution to this problem is the widespread adoption of nuclear breeder reactor technology. Innovative breeder reactor concepts using liquid-metal coolants such as sodium or lead will be able to utilize the waste produced by the current light water reactor fuel cycle to power the entire world for several centuries to come. Breed & burn (B & B) type fast reactor cores can unlock the energy potential of readily available fertile material such as depleted uranium without the need for chemical reprocessing. Using B & B technology, nuclear waste generation, uranium mining needs and proliferation concerns can be greatly reduced, and after a transitional period, enrichment facilities may no longer be needed. In this dissertation, new passively operating safety systems for fast reactors cores are presented. New analysis and optimization methods for B & B core design have been developed, along with a comprehensive computer code that couples neutronics, thermal-hydraulics and structural mechanics and enables a completely automated and optimized fast reactor core design process. In addition, an experiment that expands the knowledge-base of corrosion issues of lead-based coolants in nuclear reactors was designed and built. The motivation behind the work presented in this thesis is to help facilitate the widespread adoption of safe and efficient fast reactor technology.
Book Synopsis Compendium of Computer Codes for the Safety Analysis of Fast Breeder Reactors by :
Download or read book Compendium of Computer Codes for the Safety Analysis of Fast Breeder Reactors written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of the compendium is to provide the reader with a guide which briefly describes many of the computer codes used for liquid metal fast breeder reactor safety analyses, since it is for this system that most of the codes have been developed. The compendium is designed to address the following frequently asked questions from individuals in licensing and research and development activities: (1) What does the code do. (2) To what safety problems has it been applied. (3) What are the code's limitations. (4) What is being done to remove these limitations. (5) How does the code compare with experimental observations and other code predictions. (6) What reference documents are available.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 632 pages. Available in PDF, EPUB and Kindle. Book excerpt: NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.