Status Of Preconceptual Design Of The Advanced High Temperature Reactor Ahtr

Download Status Of Preconceptual Design Of The Advanced High Temperature Reactor Ahtr full books in PDF, epub, and Kindle. Read online Status Of Preconceptual Design Of The Advanced High Temperature Reactor Ahtr ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!

Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR).

Author : D. T. Ingersoll
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)

DOWNLOAD NOW!

Book Synopsis Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR). by : D. T. Ingersoll

Download or read book Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR). written by D. T. Ingersoll and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A new reactor plant concept is presented that combines the benefits of ceramic-coated, high-temperature particle fuel with those of clean, high-temperature, low-pressure molten salt coolant. The Advanced High-Temperature Reactor (AHTR) concept is a collaboration of Oak Ridge National Laboratory, Sandia National Laboratories, and the University of California at Berkeley. The purpose of the concept is to provide an advanced design capable of satisfying the top-level functional requirements of the U.S. Department of Energy Next Generation Nuclear Plant (NGNP), while also providing a technology base that is sufficiently robust to allow future development paths to higher temperatures and larger outputs with highly competitive economics. This report summarizes the status of the AHTR preconceptual design. It captures the results from an intense effort over a period of 3 months to (1) screen and examine potential feasibility concerns with the concept; (2) refine the conceptual design of major systems; and (3) identify research, development, and technology requirements to fully mature the AHTR design. Several analyses were performed and are presented to quantify the AHTR performance expectations and to assist in the selection of several design parameters. The AHTR, like other NGNP reactor concepts, uses coated particle fuel in a graphite matrix. But unlike the other NGNP concepts, the AHTR uses molten salt rather than helium as the primary system coolant. The considerable previous experience with molten salts in nuclear environments is discussed, and the status of high-temperature materials is reviewed. The large thermal inertia of the system, the excellent heat transfer and fission product retention characteristics of molten salt, and the low-pressure operation of the primary system provide significant safety attributes for the AHTR. Compared with helium coolant, a molten salt cooled reactor will have significantly lower fuel temperatures (150-200-C lower) for the equivalent temperature of heat delivered to either the power conversion system or a hydrogen production plant. Using a comparative cost analysis, the construction costs per unit output are projected to be 50-55% of the costs for modular gas-cooled or sodium-cooled reactor systems. This is primarily a consequence of substantially larger power output and higher conversion efficiency for the AHTR. The AHTR has a number of unique technical challenges in meeting the NGNP requirements; however, it appears to offer advantages over high-temperature helium-cooled reactors and provides an alternative development path to achieve the NGNP requirements. Primary challenges include optimizing the core design for improved response to transients, designing an internal blanket to thermally protect the reactor vessel, and engineering solutions to high-temperature refueling and maintenance.

Advanced High Temperature Reactor Systems and Economic Analysis

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (873 download)

DOWNLOAD NOW!

Book Synopsis Advanced High Temperature Reactor Systems and Economic Analysis by :

Download or read book Advanced High Temperature Reactor Systems and Economic Analysis written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced High Temperature Reactor (AHTR) is a design concept for a large-output [3400 MW(t)] fluoride-salt-cooled high-temperature reactor (FHR). FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The AHTR's large thermal output enables direct comparison of its performance and requirements with other high output reactor concepts. As high-temperature plants, FHRs can support either high-efficiency electricity generation or industrial process heat production. The AHTR analysis presented in this report is limited to the electricity generation mission. FHRs, in principle, have the potential to be low-cost electricity producers while maintaining full passive safety. However, no FHR has been built, and no FHR design has reached the stage of maturity where realistic economic analysis can be performed. The system design effort described in this report represents early steps along the design path toward being able to predict the cost and performance characteristics of the AHTR as well as toward being able to identify the technology developments necessary to build an FHR power plant. While FHRs represent a distinct reactor class, they inherit desirable attributes from other thermal power plants whose characteristics can be studied to provide general guidance on plant configuration, anticipated performance, and costs. Molten salt reactors provide experience on the materials, procedures, and components necessary to use liquid fluoride salts. Liquid metal reactors provide design experience on using low-pressure liquid coolants, passive decay heat removal, and hot refueling. High temperature gas-cooled reactors provide experience with coated particle fuel and graphite components. Light water reactors (LWRs) show the potentials of transparent, high-heat capacity coolants with low chemical reactivity. Modern coal-fired power plants provide design experience with advanced supercritical-water power cycles. The current design activities build upon a series of small-scale efforts over the past decade to evaluate and describe the features and technology variants of FHRs. Key prior concept evaluation reports include the SmAHTR preconceptual design report,1 the PB-AHTR preconceptual design, and the series of early phase AHTR evaluations performed from 2004 to 2006. This report provides a power plant-focused description of the current state of the AHTR. The report includes descriptions and sizes of the major heat transport and power generation components. Component configuration and sizing are based upon early phase AHTR plant thermal hydraulic models. The report also provides a top-down AHTR comparative economic analysis. A commercially available advanced supercritical water-based power cycle was selected as the baseline AHTR power generation cycle both due to its superior performance and to enable more realistic economic analysis. The AHTR system design, however, has several remaining gaps, and the plant cost estimates consequently have substantial remaining uncertainty. For example, the enriched lithium required for the primary coolant cannot currently be produced on the required scale at reasonable cost, and the necessary core structural ceramics do not currently exist in a nuclear power qualified form. The report begins with an overview of the current, early phase, design of the AHTR plant. Only a limited amount of information is included about the core and vessel as the core design and refueling options are the subject of a companion report. The general layout of an AHTR system and site showing the relationship of the major facilities is then provided. Next is a comparative evaluation of the AHTR anticipated performance and costs. Finally, the major system design efforts necessary to bring the AHTR design to a pre-conceptual level are then presented.

Current Status of the Advanced High Temperature Reactor

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (16 download)

DOWNLOAD NOW!

Book Synopsis Current Status of the Advanced High Temperature Reactor by :

Download or read book Current Status of the Advanced High Temperature Reactor written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced High Temperature Reactor (AHTR) is a design concept for a central station type [1500 MW(e)] Fluoride salt-cooled High-temperature Reactor (FHR) that is currently under development by Oak Ridge National Laboratory for the U.S. Department of Energy, Office of Nuclear Energy's Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR design option exploration is a multidisciplinary design effort that combines core neutronic and fuel configuration evaluation with structural, thermal, and hydraulic analysis to produce a reactor and vessel concept and place it within a power generation station. The AHTR design remains at the notional level of maturity, as key technologies require further development and a logically complete integrated design has not been finalized. The present design space exploration, however, indicates that reasonable options exist for the AHTR core, primary heat transport path, and fuel cycle provided that materials and systems technologies develop as anticipated.

Advanced High-Temperature Reactor Dynamic System Model Development

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (946 download)

DOWNLOAD NOW!

Book Synopsis Advanced High-Temperature Reactor Dynamic System Model Development by :

Download or read book Advanced High-Temperature Reactor Dynamic System Model Development written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced High-Temperature Reactor (AHTR) is a large-output fluoride-salt-cooled high-temperature reactor (FHR). An early-phase preconceptual design of a 1500 MW(e) power plant was developed in 2011 [Refs. 1 and 2]. An updated version of this plant is shown as Fig. 1. FHRs feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The AHTR is designed to be a "walk away" reactor that requires no action to prevent large off-site releases following even severe reactor accidents. This report describes the development of dynamic system models used to further the AHTR design toward that goal. These models predict system response during warmup, startup, normal operation, and limited off-normal operating conditions. Severe accidents that include a loss-of-fluid inventory are not currently modeled. The scope of the models is limited to the plant power system, including the reactor, the primary and intermediate heat transport systems, the power conversion system, and safety-related or auxiliary heat removal systems. The primary coolant system, the intermediate heat transport system and the reactor building structure surrounding them are shown in Fig. 2. These systems are modeled in the most detail because the passive interaction of the primary system with the surrounding structure and heat removal systems, and ultimately the environment, protects the reactor fuel and the vessel from damage during severe reactor transients. The reactor silo also plays an important role during system warmup. The dynamic system modeling tools predict system performance and response. The goal is to accurately predict temperatures and pressures within the primary, intermediate, and power conversion systems and to study the impacts of design changes on those responses. The models are design tools and are not intended to be used in reactor qualification. The important details to capture in the primary system relate to flows within the reactor vessel during severe events and the resulting temperature profiles (temperature and duration) for major components. Critical components include the fuel, reactor vessel, primary piping, and the primary-to-intermediate heat exchangers (P-IHXs). The major AHTR power system loops are shown in Fig. 3. The intermediate heat transfer system is a group of three pumped salt loops that transports the energy produced in the primary system to the power conversion system. Two dynamic system models are used to analyze the AHTR. A Matlab/Simulink-based model initiated in 2011 has been updated to reflect the evolving design parameters related to the heat flows associated with the reactor vessel. The Matlab model utilizes simplified flow assumptions within the vessel and incorporates an empirical representation of the Direct Reactor Auxiliary Cooling System (DRACS). A Dymola/Modelica model incorporates a more sophisticated representation of primary coolant flow and a physics-based representation of the three-loop DRACS thermal hydraulics. This model is not currently operating in a fully integrated mode. The Matlab model serves as a prototype and provides verification for the Dymola model, and its use will be phased out as the Dymola model nears completion. The heat exchangers in the system are sized using spreadsheet-based, steady-state calculations. The detail features of the heat exchangers are programmed into the dynamic models, and the overall dimensions are used to generate realistic plant designs. For the modeling cases where the emphasis is on understanding responses within the intermediate and primary systems, the power conversion system may be modeled as a simple boundary condition at the intermediate-to-power conversion system heat exchangers.

Core and Refueling Design Studies for the Advanced High Temperature Reactor

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (873 download)

DOWNLOAD NOW!

Book Synopsis Core and Refueling Design Studies for the Advanced High Temperature Reactor by :

Download or read book Core and Refueling Design Studies for the Advanced High Temperature Reactor written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced High Temperature Reactor (AHTR) is a design concept for a central generating station type [3400 MW(t)] fluoride-salt-cooled high-temperature reactor (FHR). The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. This report presents the current status of ongoing design studies of the core, in-vessel structures, and refueling options for the AHTR. The AHTR design remains at the notional level of maturity as important material, structural, neutronic, and hydraulic issues remain to be addressed. The present design space exploration, however, indicates that reasonable options exist for the AHTR core, primary heat transport path, and fuel cycle provided that materials and systems technologies develop as anticipated. An illustration of the current AHTR core, reactor vessel, and nearby structures is shown in Fig. ES1. The AHTR core design concept is based upon 252 hexagonal, plate fuel assemblies configured to form a roughly cylindrical core. The core has a fueled height of 5.5 m with 25 cm of reflector above and below the core. The fuel assembly hexagons are ≈45 cm across the flats. Each fuel assembly contains 18 plates that are 23.9 cm wide and 2.55 cm thick. The reactor vessel has an exterior diameter of 10.48 m and a height of 17.7 m. A row of replaceable graphite reflector prismatic blocks surrounds the core radially. A more complete reactor configuration description is provided in Section 2 of this report. The AHTR core design space exploration was performed under a set of constraints. Only low enrichment (

Nuclear Hydrogen Production Handbook

Author : Xing L. Yan
Publisher : CRC Press
ISBN 13 : 1439810842
Total Pages : 939 pages
Book Rating : 4.4/5 (398 download)

DOWNLOAD NOW!

Book Synopsis Nuclear Hydrogen Production Handbook by : Xing L. Yan

Download or read book Nuclear Hydrogen Production Handbook written by Xing L. Yan and published by CRC Press. This book was released on 2016-04-19 with total page 939 pages. Available in PDF, EPUB and Kindle. Book excerpt: Written by two leading researchers from the world-renowned Japan Atomic Energy Agency, the Nuclear Hydrogen Production Handbook is an unrivalled overview of current and future prospects for the effective production of hydrogen via nuclear energy. Combining information from scholarly analyses, industrial data, references, and other resources, this h

Numerical and Experimental Studies on Small/Micro Nuclear Reactors

Author : Yugao Ma
Publisher : Frontiers Media SA
ISBN 13 : 2832547036
Total Pages : 133 pages
Book Rating : 4.8/5 (325 download)

DOWNLOAD NOW!

Book Synopsis Numerical and Experimental Studies on Small/Micro Nuclear Reactors by : Yugao Ma

Download or read book Numerical and Experimental Studies on Small/Micro Nuclear Reactors written by Yugao Ma and published by Frontiers Media SA. This book was released on 2024-04-01 with total page 133 pages. Available in PDF, EPUB and Kindle. Book excerpt: Future space missions and deep-sea explorations will require small/micro nuclear reactors (kWe~MWe) for power generation. Compared with conventional energy systems such as storage batteries and fossil energy, nuclear reactors are featured higher energy intensity, higher reliability, and longer lifetime. According to the coolant, the candidate small/micro nuclear reactors include the heat pipe cooled reactor, liquid metal cooled reactor, and gas-cooled reactor, most of which are still in the conceptual design stage with numerical studies and experimental research. These emerging reactors have an entirely different core structure and working principle from the existing light water reactors, which has led to an increasing need for updated simulation methods and experimental studies.

Molten Salt Reactors and Thorium Energy

Author : Thomas James Dolan
Publisher : Elsevier
ISBN 13 : 0323993567
Total Pages : 1068 pages
Book Rating : 4.3/5 (239 download)

DOWNLOAD NOW!

Book Synopsis Molten Salt Reactors and Thorium Energy by : Thomas James Dolan

Download or read book Molten Salt Reactors and Thorium Energy written by Thomas James Dolan and published by Elsevier. This book was released on 2024-01-25 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts Covers MSR applications, technical issues, reactor types and reactor designs Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe

Proceedings of The 20th Pacific Basin Nuclear Conference

Author : Hong Jiang
Publisher : Springer
ISBN 13 : 9811023174
Total Pages : 901 pages
Book Rating : 4.8/5 (11 download)

DOWNLOAD NOW!

Book Synopsis Proceedings of The 20th Pacific Basin Nuclear Conference by : Hong Jiang

Download or read book Proceedings of The 20th Pacific Basin Nuclear Conference written by Hong Jiang and published by Springer. This book was released on 2017-01-29 with total page 901 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is the second in a series of three proceedings of the 20th Pacific Basin Nuclear Conference (PBNC). This volume covers the topics of Operation and Maintenance, Supply Capability and Quality Control, Fuel Cycles, as well as New Technology and New Applications. As one in the most important and influential conference series of nuclear science and technology, the 20th PBNC was held in Beijing and the theme of this meeting was “Nuclear: Powering the Development of the Pacific Basin and the World”. It brought together outstanding nuclear scientist and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The book is not only a good summary of the new developments in the field, but also a useful guideline for the researchers, engineers and graduate students.

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Author : Jyeshtharaj Joshi
Publisher : Woodhead Publishing
ISBN 13 : 0081023375
Total Pages : 888 pages
Book Rating : 4.0/5 (81 download)

DOWNLOAD NOW!

Book Synopsis Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment by : Jyeshtharaj Joshi

Download or read book Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment written by Jyeshtharaj Joshi and published by Woodhead Publishing. This book was released on 2019-06-15 with total page 888 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization

Nuclear Energy

Author : Nicholas Tsoulfanidis
Publisher : Springer Science & Business Media
ISBN 13 : 1461457165
Total Pages : 522 pages
Book Rating : 4.4/5 (614 download)

DOWNLOAD NOW!

Book Synopsis Nuclear Energy by : Nicholas Tsoulfanidis

Download or read book Nuclear Energy written by Nicholas Tsoulfanidis and published by Springer Science & Business Media. This book was released on 2012-12-12 with total page 522 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Energy provides an authoritative reference on all aspects of the nuclear industry from fundamental reactor physics calculations to reactor design, nuclear fuel resources, nuclear fuel cycle, radiation detection and protection, and nuclear power economics. Featuring 19 peer-reviewed entries by recognized authorities in the field, this book provides comprehensive, streamlined coverage of fundamentals, current areas of research, and goals for the future. The chapters will appeal to undergraduate and graduate students, researchers, and energy industry experts.

Molten Salts 15

Author : Robert A. Mantz
Publisher : The Electrochemical Society
ISBN 13 : 1566775922
Total Pages : 629 pages
Book Rating : 4.5/5 (667 download)

DOWNLOAD NOW!

Book Synopsis Molten Salts 15 by : Robert A. Mantz

Download or read book Molten Salts 15 written by Robert A. Mantz and published by The Electrochemical Society. This book was released on 2007 with total page 629 pages. Available in PDF, EPUB and Kindle. Book excerpt: This symposium was dedicated to the significant and ground breaking accomplishments of Robert A. Osteryoung in the area of molten salts and ionic liquids. This symposium provided an international and interdisciplinary forum centered on innovative basic and applied research performed in molten salts and ionic liquids. Contributed papers were solicited in all areas of biology, chemistry, electrochemistry, electrochemical engineering, and physics related to molten salt research.

AHTR Refueling Systems and Process Description

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (953 download)

DOWNLOAD NOW!

Book Synopsis AHTR Refueling Systems and Process Description by :

Download or read book AHTR Refueling Systems and Process Description written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW(e)] Fluoride salt-cooled High-temperature Reactor (FHR) that is currently undergoing development by Oak Ridge National Laboratory for the US. Department of Energy, Office of Nuclear Energy's Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR is approaching a preconceptual level of maturity. An initial integrated layout of its major systems, structures, and components (SSCs), and an initial, high-level sequence of operations necessary for constructing and operating the plant is nearing completion. An overview of the current status of the AHTR concept has been recently published [1], and a report providing a more detailed overview of the AHTR structures and mechanical systems is currently in preparation. This report documents the refueling components and processes envisioned at this early development phase. The report is limited to the refueling aspects of the AHTR and does not include overall reactor or power plant design information. The report, however, does include a description of the materials envisioned for the various components and the instrumentation necessary to control the refueling process. The report begins with an overview of the refueling strategy. Next a mechanical description of the AHTR fuel assemblies and core is provided. The reactor vessel upper assemblies are then described. Following this the refueling path structures and the refueling mechanisms and components are described. The sequence of operations necessary to fuel and defuel the reactor is then discussed. The report concludes with a discussion of the levels of maturity of the various SSCs to provide guidance for future technology developments. The conceptual design information presented in this report is very preliminary in nature. Significant uncertainty remains about several aspects of the process and even the radiation and mechanical performance of plate-type coated-particle fuel.

AHTR Mechanical, Structural, And Neutronic Preconceptual Design

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (946 download)

DOWNLOAD NOW!

Book Synopsis AHTR Mechanical, Structural, And Neutronic Preconceptual Design by :

Download or read book AHTR Mechanical, Structural, And Neutronic Preconceptual Design written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report provides an overview of the mechanical, structural, and neutronic aspects of the Advanced High Temperature Reactor (AHTR) design concept. The AHTR is a design concept for a large output Fluoride salt cooled High-temperature Reactor (FHR) that is being developed to enable evaluation of the technology hurdles remaining to be overcome prior to FHRs becoming a commercial reactor class. This report documents the incremental AHTR design maturation performed over the past year and is focused on advancing the design concept to a level of a functional, self-consistent system. The AHTR employs plate type coated particle fuel assemblies with rapid, off-line refueling. Neutronic analysis of the core has confirmed the viability of a 6-month 2-batch cycle with 9 weight-percent enriched uranium fuel. Refueling is intended to be performed automatically under visual guidance using dedicated robotic manipulators. The present design intent is for used fuel to be stored inside of containment for at least 6 months and then transferred to local dry wells for intermediate term, on-site storage. The mechanical and structural concept development effort has included an emphasis on transportation and constructability to minimize construction costs and schedule. The design intent is that all components be factory fabricated into rail transportable modules that are assembled into subsystems at an on-site workshop prior to being lifted into position using a heavy-lift crane in an open-top style construction. While detailed accident identification and response sequence analysis has yet to be performed, the design concept incorporates multiple levels of radioactive material containment including fully passive responses to all identified design basis or non-very-low frequency beyond design basis accidents. Key building design elements include: 1) below grade siting to minimize vulnerability to aircraft impact, 2) multiple natural circulation decay heat rejection chimneys, 3) seismic base isolation, and 4) decay heat powered back-up electricity generation. The report provides a preconceptual design of the manipulators, the fuel transfer system, and the salt transfer loops. The mechanical handling of the fuel and how it is accomplished without instrumentation inside the salt is described within the report. All drives for the manipulators reside outside the reactor top flange. The design has also taken into account the transportability of major components and how they will be assembled on site.

Bericht über die Feier

Author :
Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.:/5 (444 download)

DOWNLOAD NOW!

Book Synopsis Bericht über die Feier by :

Download or read book Bericht über die Feier written by and published by . This book was released on 1929 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Corrosion Science and Engineering

Author : Damien Feron
Publisher : Elsevier
ISBN 13 : 085709534X
Total Pages : 1073 pages
Book Rating : 4.8/5 (57 download)

DOWNLOAD NOW!

Book Synopsis Nuclear Corrosion Science and Engineering by : Damien Feron

Download or read book Nuclear Corrosion Science and Engineering written by Damien Feron and published by Elsevier. This book was released on 2012-02-21 with total page 1073 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches

Status of Innovative Small and Medium Sized Reactor Designs 2005

Author : International Atomic Energy Agency
Publisher : IAEA
ISBN 13 :
Total Pages : 728 pages
Book Rating : 4.3/5 (91 download)

DOWNLOAD NOW!

Book Synopsis Status of Innovative Small and Medium Sized Reactor Designs 2005 by : International Atomic Energy Agency

Download or read book Status of Innovative Small and Medium Sized Reactor Designs 2005 written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 728 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this report is to provide Member States, including those just considering the initiation of nuclear power programmes and those already having practical experience in nuclear power, with balanced and objective information on important development trends and objectives of innovative small and medium sized reactors (SMRs) for a variety of uses, on the achieved state-of-the-art in design and technology development for such reactors and on their design and regulatory status. The publication is intended for many categories of stakeholders, including regulators, electricity producers, designers, non-electricity producers and policy makers. The main sections of this publication, addressed to all the above mentioned groups of stakeholders, provide a summary of major specifications, applications and user-related special features of innovative SMRs. The annexes, intended mainly for designers and technical managers, provide detailed design descriptions of innovative SMRs, focusing on their potential to provide solutions in the areas of concern associated with future nuclear energy systems