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Book Optimisation of Sodium cooled Fast Reactors

Download or read book Optimisation of Sodium cooled Fast Reactors written by Joyce S. Davis and published by Thomas Telford Publishing. This book was released on 1978 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Optimisation of Sodium cooled Fast Reactors

Download or read book Optimisation of Sodium cooled Fast Reactors written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Optimisation of Sodium cooled Fast Reactors

Download or read book Optimisation of Sodium cooled Fast Reactors written by C.E. Iliffe and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Safety of Sodium Cooled Fast Reactors

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 Optimisation of sodium cooled fast reactors

Download or read book Optimisation of sodium cooled fast reactors written by Joyce S. Davis and published by . This book was released on 1978 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Analysis of Accidents in Sodium cooled Fast Reactors

Download or read book Analysis of Accidents in Sodium cooled Fast Reactors written by Whitney Ann Wutzler and published by . This book was released on 2011 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: The research presented in this paper is part of a project to help develop a risk-informed approach to the design optimization and licensing of a sodium-cooled fast reactor (SFR). The objectives of this research include analyzing accident scenarios that occur in SFRs and assessing their offsite consequences.

Book Final Report passive Safety Optimization in Liquid Sodium cooled Reactors

Download or read book Final Report passive Safety Optimization in Liquid Sodium cooled Reactors written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes the results of a three-year collaboration between Argonne National Laboratory (ANL) and the Korea Atomic Energy Research Institute (KAERI) to identify and quantify the performance of innovative design features in metallic-fueled, sodium-cooled fast reactor designs. The objective of the work was to establish the reliability and safety margin enhancements provided by design innovations offering significant potential for construction, maintenance, and operating cost reductions. The project goal was accomplished with a combination of advanced model development (Task 1), analysis of innovative design and safety features (Tasks 2 and 3), and planning of key safety experiments (Task 4). Task 1--Computational Methods for Analysis of Passive Safety Design Features: An advanced three-dimensional subassembly thermal-hydraulic model was developed jointly and implemented in ANL and KAERI computer codes. The objective of the model development effort was to provide a high-accuracy capability to predict fuel, cladding, coolant, and structural temperatures in reactor fuel subassemblies, and thereby reduce the uncertainties associated with lower fidelity models previously used for safety and design analysis. The project included model formulation, implementation, and verification by application to available reactor tests performed at EBR-II. Task 2--Comparative Analysis and Evaluation of Innovative Design Features: Integrated safety assessments of innovative liquid metal reactor designs were performed to quantify the performance of inherent safety features. The objective of the analysis effort was to identify the potential safety margin enhancements possible in a sodium-cooled, metal-fueled reactor design by use of passive safety mechanisms to mitigate low-probability accident consequences. The project included baseline analyses using state-of-the-art computational models and advanced analyses using the new model developed in Task 1. Task 3--Safety Implications of Advanced Technology Power Conversion and Design Innovations and Simplifications: Investigations of supercritical CO2 gas turbine Brayton cycles coupled to the sodium-cooled reactors and innovative concepts for sodium-to-CO2 heat exchangers were performed to discover new designs for high efficiency electricity production. The objective of the analyses was to characterize the design and safety performance of equipment needed to implement the new power cycle. The project included considerations of heat transfer and power conversion systems arrangements and evaluations of systems performance. Task 4--Post Accident Heat Removal and In-Vessel Retention: Test plans were developed to evaluate (1) freezing and plugging of molten metallic fuel in subassembly geometry, (2) retention of metallic fuel core melt debris within reactor vessel structures, and (3) consequences of intermixing of high pressure CO2 and sodium. The objective of the test plan development was to provide planning for measurements of data needed to characterize the consequences of very low probability accident sequences unique to metallic fuel and CO2 Brayton power cycles. The project produced three test plans ready for execution.

Book Sodium Fast Reactors with Closed Fuel Cycle

Download or read book Sodium Fast Reactors with Closed Fuel Cycle written by Baldev Raj and published by CRC Press. This book was released on 2015-04-15 with total page 901 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book:Offers in-depth coverage of reactor physics, materials, design, s

Book Feasibility Study of a 1000 Mwe Sodium cooled Fast Reactor  Research and development program

Download or read book Feasibility Study of a 1000 Mwe Sodium cooled Fast Reactor Research and development program written by North American Aviation. Atomics International Division and published by . This book was released on 1966 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Industrial Sodium Cooled Fast Reactor

Download or read book The Industrial Sodium Cooled Fast Reactor written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper investigates the use of enrichment and moderator zoning methods for optimizing the r-z power distribution within sodium cooled fast reactors. These methods allow overall greater fuel utilization in the core resulting in more fuel being irradiated near the maximum allowed thermal power. The peak-to-average power density was held to 1.18. This core design, in conjunction with a multiple-reheat Brayton power conversion system, has merit for producing an industrial level of electrical output (2400MWth, 1000MWe) from a relatively compact core size. The total core radius, including reflectors and shields, was held to 1.78m. Preliminary safety analysis suggests that positive reactivity insertion resulting from a leak between the sodium primary loop and helium power conversion system can be mitigated using simple gas-liquid centripetal separation strategies in the plant's primary loop.

Book Coolant Mixing in Sodium Cooled Fast Reactor Fuel Bundles

Download or read book Coolant Mixing in Sodium Cooled Fast Reactor Fuel Bundles written by Neil E. Todreas and published by . This book was released on 1968 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Feasibility Study of a 1000 Mwe Sodium cooled Fast Reactor  Methods development

Download or read book Feasibility Study of a 1000 Mwe Sodium cooled Fast Reactor Methods development written by North American Aviation. Atomics International Division and published by . This book was released on 1966 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Safety of Sodium Cooled Fast Reactors  Molten pool Mobility  Chapter 3 Molten pool Sloshing Motion  Chapter 4  Debris Bed Formation Behavior

Download or read book Safety of Sodium Cooled Fast Reactors Molten pool Mobility Chapter 3 Molten pool Sloshing Motion Chapter 4 Debris Bed Formation Behavior written by Songbai Cheng and published by . This book was released on 2021 with total page 0 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 Fast Spectrum Reactors

Download or read book Fast Spectrum Reactors written by Alan E. Waltar and published by Springer Science & Business Media. This book was released on 2011-09-28 with total page 717 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).

Book OPTIMIZATION STUDIES ON PASTE FUELED FAST REACTORS

Download or read book OPTIMIZATION STUDIES ON PASTE FUELED FAST REACTORS written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The reference design is an unmoderated, sodium-cooled reactor using a paste fuel of uranium monocarbide in sodium. The core is a cylinder 5 ft in diameter and 5 ft in height. An 18-in. thick breeding blanket surrounds the core, and an 18-in. thick graphite reflector surrounds the blanket. Various changes were made in the reference core to uncover any possible modifications for cost reductions and to evaluate the consequences of certain design modifications which might occur. Cases were studied for variations in: fuel volume fraction in the core from 0.2 to 0.6; fertile material volume fraction in the blanket from 0.2 to 0.6; blanket thickness 3 in. to 24 in.; fuel materials of UC, U metal, UC/ sub 2/, PuC-- UC, Pu-- U metal, and PuO2-- UC2; and liquid carrier in the paste of Na, Sn, or Pb. (auth).

Book Design Considerations for Economically Competitive Sodium Cooled Fast Reactors

Download or read book Design Considerations for Economically Competitive Sodium Cooled Fast Reactors written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The technological viability of sodium cooled fast reactors (SFR) has been established by various experimental and prototype (demonstration) reactors such as EBR-II, FFTF, Phénix, JOYO, BN-600 etc. However, the economic competitiveness of SFR has not been proven yet. The perceived high cost premium of SFRs over LWRs has been the primary impediment to the commercial expansion of SFR technologies. In this paper, cost reduction options are discussed for advanced SFR designs. These include a hybrid loop-pool design to optimize the primary system, multiple reheat and intercooling helium Brayton cycle for the power conversion system and the potential for suppression of intermediate heat transport system. The design options for the fully passive decay heat removal systems are also thoroughly examined. These include direct reactor auxiliary cooling system (DRACS), reactor vessel auxiliary cooling system (RVACS) and the newly proposed pool reactor auxiliary cooling system (PRACS) in the context of the hybrid loop-pool design.