Flexible Conversion Ratio Fast Reactor Systems Evaluation

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Flexible Conversion Ratio Fast Reactor Systems Evaluation by :

Download or read book Flexible Conversion Ratio Fast Reactor Systems Evaluation written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Conceptual designs of lead-cooled and liquid salt-cooled fast flexible conversion ratio reactors were developed. Both concepts have cores reated at 2400 MWt placed in a large-pool-type vessel with dual-free level, which also contains four intermediate heat exchanges coupling a primary coolant to a compact and efficient supercritical CO2 Brayton cycle power conversion system. Decay heat is removed passively using an enhanced Reactor Vessel Auxiliary Cooling System and a Passive Secondary Auxiliary Cooling System. The most important findings were that (1) it is feasible to design the lead-cooled and salt-cooled reactor with the flexible conversion ratio (CR) in the range of CR=0 and CR=1 n a manner that achieves inherent reactor shutdown in unprotected accidents, (2) the salt-cooled reactor requires Lithium thermal Expansion Modules to overcme the inherent salt coolant's large positive coolant temperature reactivity coefficient, (3) the preferable salt for fast spectrum high power density cores is NaCl-Kcl-MgCl2 as opposed to fluoride salts due to its better themal-hydraulic and neutronic characteristics, and (4) both reactor, but attain power density 3 times smaller than that of the sodium-cooled reactor.

Large Lead-cooled Reactor with Flexible Conversion Ratio

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ISBN 13 :
Total Pages : 200 pages
Book Rating : 4.:/5 (547 download)

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Book Synopsis Large Lead-cooled Reactor with Flexible Conversion Ratio by : Anna S. Nikiforova (S.M.)

Download or read book Large Lead-cooled Reactor with Flexible Conversion Ratio written by Anna S. Nikiforova (S.M.) and published by . This book was released on 2008 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) The transient simulation of station blackout (SBO) using the RELAP5-3D/ATHENA code shows that inherent shutdown without scram can be accommodated within the cladding temperature limit by the enhanced RVACS and PSACS by removing a fraction of decay power with the PSACS. The PSACS was designed such that the balance between two limiting cases was achieved: (1) peak cladding temperature limit is satisfied during unprotected station blackout with a minimum (two) number of PSACS trains operated, and (2) the minimum coolant temperature is kept above the freezing point with a maximum (four) number of PSACS trains operated. The PSACS design satisfies the conditions of both unity and zero conversion ratio cores. The other SBO accident conditions are bounded by the above cases. In addition, two other transients are considered: loss-of-flow accident (LOFA) and inadvertent reactivity insertion transient (UTOP). Both reactors show good performance during these additional transients.

Design of Passive Decay Heat Removal System for the Lead Cooled Flexible Conversion Ratio Fast Reactor

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ISBN 13 :
Total Pages : 78 pages
Book Rating : 4.:/5 (221 download)

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Book Synopsis Design of Passive Decay Heat Removal System for the Lead Cooled Flexible Conversion Ratio Fast Reactor by : Joshua J. Whitman

Download or read book Design of Passive Decay Heat Removal System for the Lead Cooled Flexible Conversion Ratio Fast Reactor written by Joshua J. Whitman and published by . This book was released on 2007 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt: The lead-cooled flexible conversion ratio fast reactor shows many benefits over other fast-reactor designs; however, the higher power rating and denser primary coolant present difficulties for the design of a passive decay heat removal system. In order to achieve passive cooling, enhancements are needed over current designs, such as the S-PRISM and ABR, which utilize passive cooling through the reactor vessel to atmospheric air. Enhancements such as axial fins, a perforated plate, and round indentations, or dimples, were considered as additions to the hot air riser to increase heat transfer. Other enhancements include a liquid metal bond between the reactor and guard vessels, and a dual-level design which introduces ambient temperature air halfway up the vessel wall. A code was written in Java to simulate these conditions, leading to a promising case using dimples on the guard vessel wall as the primary mode of heat transfer enhancement, and including the dual-level design. A conservative estimate of dimple performance indicates that during a passive decay heat removal shutdown, bulk primary coolant temperature will peak at 713 'C, giving a 12 OC margin to clad failure. Attempts were made to refine the uncertainty within the calculations using a computational fluid dynamics code, Fluent, but these ultimately were unsuccessful. Additional studies were conducted on the static stress imparted on the vessel, and the dynamic stress caused by a seismic event. The static stress was found to be within ASME code limits. Seismic analysis determined that a seismic isolation scheme would be necessary in order to prevent damage to the vessel during an earthquake.

Design of a 2400MW Liquid-salt Cooled Flexible Conversion Ratio Reactor

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ISBN 13 :
Total Pages : 145 pages
Book Rating : 4.:/5 (547 download)

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Book Synopsis Design of a 2400MW Liquid-salt Cooled Flexible Conversion Ratio Reactor by : Robert C. Petroski

Download or read book Design of a 2400MW Liquid-salt Cooled Flexible Conversion Ratio Reactor written by Robert C. Petroski and published by . This book was released on 2008 with total page 145 pages. Available in PDF, EPUB and Kindle. Book excerpt: A 2400MWth liquid-salt cooled flexible conversion ratio reactor was designed, utilizing the ternary chloride salt NaCl-KCl-MgCI2 (30%-20%-50%) as coolant. The reference design uses a wire-wrapped, hex lattice core, and is able to achieve a core power density of 130 kW/1 with a core pressure drop of 700kPa and a maximum cladding temperature under 650'C. Four kidney- shaped conventional tube-in-shell heat exchangers are used to connect the primary system to a 5450C supercritical CO2 power conversion system. The core, intermediate heat exchangers, and reactor coolant pumps fit in a vessel approximately 10 meters in diameter and less than 20 meters high. Lithium expansion modules (LEMs) were used to reconcile conflicting thermal hydraulic and reactor physics requirements in the liquid salt core. Use of LEMs allowed the design of a very favorable reactivity response which greatly benefits transient mitigation. A reactor vessel auxiliary cooling system (RVACS) and four redundant passive secondary auxiliary cooling systems (PSACS) are used to provide passive heat removal, and are able to successfully mitigate both an unprotected station blackout transient as well as protected transients in which a scram occurs. Additionally, it was determined that the power conversion system can be used to mitigate both a loss of flow accident and an unprotected transient overpower.

Handbook of Generation IV Nuclear Reactors

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Publisher : Woodhead Publishing
ISBN 13 : 0128226536
Total Pages : 1112 pages
Book Rating : 4.1/5 (282 download)

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Book Synopsis Handbook of Generation IV Nuclear Reactors by : Igor Pioro

Download or read book Handbook of Generation IV Nuclear Reactors written by Igor Pioro and published by Woodhead Publishing. This book was released on 2022-12-07 with total page 1112 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors Includes new trends and developments since the first publication, as well as brand new case studies and appendices Covers the latest research, developments and design information surrounding generation IV nuclear reactors

Issues in Water and Power Engineering: 2011 Edition

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Publisher : ScholarlyEditions
ISBN 13 : 1464965811
Total Pages : 651 pages
Book Rating : 4.4/5 (649 download)

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Book Synopsis Issues in Water and Power Engineering: 2011 Edition by :

Download or read book Issues in Water and Power Engineering: 2011 Edition written by and published by ScholarlyEditions. This book was released on 2012-01-09 with total page 651 pages. Available in PDF, EPUB and Kindle. Book excerpt: Issues in Water and Power Engineering / 2011 Edition is a ScholarlyEditions™ eBook that delivers timely, authoritative, and comprehensive information about Water and Power Engineering. The editors have built Issues in Water and Power Engineering: 2011 Edition on the vast information databases of ScholarlyNews.™ You can expect the information about Water and Power Engineering in this eBook to be deeper than what you can access anywhere else, as well as consistently reliable, authoritative, informed, and relevant. The content of Issues in Water and Power Engineering: 2011 Edition has been produced by the world’s leading scientists, engineers, analysts, research institutions, and companies. All of the content is from peer-reviewed sources, and all of it is written, assembled, and edited by the editors at ScholarlyEditions™ and available exclusively from us. You now have a source you can cite with authority, confidence, and credibility. More information is available at http://www.ScholarlyEditions.com/.

Status of Fast Reactor Research and Technology Development

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ISBN 13 : 9781523130191
Total Pages : 0 pages
Book Rating : 4.1/5 (31 download)

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Book Synopsis Status of Fast Reactor Research and Technology Development by : International Atomic Energy Agency

Download or read book Status of Fast Reactor Research and Technology Development written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "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.

Structural Materials for Generation IV Nuclear Reactors

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Publisher : Woodhead Publishing
ISBN 13 : 0081009127
Total Pages : 686 pages
Book Rating : 4.0/5 (81 download)

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Book Synopsis Structural Materials for Generation IV Nuclear Reactors by : Pascal Yvon

Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates Written by an expert in that particular area

Comparative Assessment of Thermophysical and Thermohydraulic Characteristics of Lead, Lead-Bismuth and Sodium Coolants for Fast Reactors

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ISBN 13 : 9789201136022
Total Pages : 277 pages
Book Rating : 4.1/5 (36 download)

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Book Synopsis Comparative Assessment of Thermophysical and Thermohydraulic Characteristics of Lead, Lead-Bismuth and Sodium Coolants for Fast Reactors by : IAEA

Download or read book Comparative Assessment of Thermophysical and Thermohydraulic Characteristics of Lead, Lead-Bismuth and Sodium Coolants for Fast Reactors written by IAEA and published by . This book was released on 2002-06-30 with total page 277 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Handbook of Nuclear Engineering

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Publisher : Springer Science & Business Media
ISBN 13 : 0387981306
Total Pages : 3701 pages
Book Rating : 4.3/5 (879 download)

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Book Synopsis Handbook of Nuclear Engineering by : Dan Gabriel Cacuci

Download or read book Handbook of Nuclear Engineering written by Dan Gabriel Cacuci and published by Springer Science & Business Media. This book was released on 2010-09-14 with total page 3701 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

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ISBN 13 : 9789201253101
Total Pages : 639 pages
Book Rating : 4.2/5 (531 download)

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Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency

Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Reactor Fuel Processing

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ISBN 13 :
Total Pages : 716 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis Reactor Fuel Processing by :

Download or read book Reactor Fuel Processing written by and published by . This book was released on 1958 with total page 716 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Handbook of Small Modular Nuclear Reactors

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Publisher : Woodhead Publishing
ISBN 13 : 0128239174
Total Pages : 648 pages
Book Rating : 4.1/5 (282 download)

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Book Synopsis Handbook of Small Modular Nuclear Reactors by : Daniel T. Ingersoll

Download or read book Handbook of Small Modular Nuclear Reactors written by Daniel T. Ingersoll and published by Woodhead Publishing. This book was released on 2020-10-22 with total page 648 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook of Small Modular Nuclear Reactors, Second Edition is a fully updated comprehensive reference on Small Modular Reactors (SMRs), which reflects the latest research and technological advances in the field from the last five years. Editors Daniel T. Ingersoll and Mario D. Carelli, along with their team of expert contributors, combine their wealth of collective experience to update this comprehensive handbook that provides the reader with all required knowledge on SMRs, expanding on the rapidly growing interest and development of SMRs around the globe. This book begins with an introduction to SMRs for power generation, an overview of international developments, and an analysis of Integral Pressurized Water Reactors as a popular class of SMRs. The second part of the book is dedicated to SMR technologies, including physics, components, I&C, human-system interfaces and safety aspects. Part three discusses the implementation of SMRs, covering economic factors, construction methods, hybrid energy systems and licensing considerations. The fourth part of the book provides an in-depth analysis of SMR R&D and deployment of SMRs within eight countries, including the United States, Republic of Korea, Russia, China, Argentina, and Japan. This edition includes brand new content on the United Kingdom and Canada, where interests in SMRs have increased considerably since the first edition was published. The final part of the book adds a new analysis of the global SMR market and concludes with a perspective on SMR benefits to developing economies. This authoritative and practical handbook benefits engineers, designers, operators, and regulators working in nuclear energy, as well as academics and graduate students researching nuclear reactor technologies. Presents the latest research on SMR technologies and global developments Includes new case study chapters on the United Kingdom and Canada and a chapter on global SMR markets Discusses new technologies such as floating SMRs and molten salt SMRs

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

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Publisher : IOS Press
ISBN 13 : 9781586036966
Total Pages : 160 pages
Book Rating : 4.0/5 (369 download)

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Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen

Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Liquid Metal Cooled Reactors

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ISBN 13 : 9789201079077
Total Pages : 0 pages
Book Rating : 4.0/5 (79 download)

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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.

Advanced Power Generation Systems

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Publisher : CRC Press
ISBN 13 : 1000798895
Total Pages : 457 pages
Book Rating : 4.0/5 (7 download)

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Book Synopsis Advanced Power Generation Systems by : Yatish T. Shah

Download or read book Advanced Power Generation Systems written by Yatish T. Shah and published by CRC Press. This book was released on 2022-12-21 with total page 457 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advanced Power Generation Systems: Thermal Sources evaluates advances made in heat-to-power technologies for conventional combustion heat and nuclear heat, along with natural sources of geothermal, solar, and waste heat generated from the use of different sources. These advances will render the landscape of power generation significantly different in just a few decades. This book covers the commercial viability of advanced technologies and identifies where more work needs to be done. Since power is the future of energy, these technologies will remain sustainable over a long period of time. Key Features Covers power generation and heat engines Details photovoltaics, thermo-photovoltaics, and thermoelectricity Includes discussion of nuclear and renewable energy as well as waste heat This book will be useful for advanced students, researchers, and professionals interested in power generation and energy industries.

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

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Publisher : Woodhead Publishing
ISBN 13 : 0081019815
Total Pages : 464 pages
Book Rating : 4.0/5 (81 download)

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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