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Thermal And Flow Design Of Helium Cooled Reactors
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Book Synopsis Thermal and Flow Design of Helium-cooled Reactors by : Gilbert Melese
Download or read book Thermal and Flow Design of Helium-cooled Reactors written by Gilbert Melese and published by . This book was released on 1984 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt: This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
Book Synopsis Thermal and Flow Design of Helium-cooled Reactors by :
Download or read book Thermal and Flow Design of Helium-cooled Reactors written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This book continues the American Nuclear Society's series of monographs on nuclear science and technology. Chapters of the book include information on the first-generation gas-cooled reactors; HTGR reactor developments; reactor core heat transfer; mechanical problems related to the primary coolant circuit; HTGR design bases; core thermal design; gas turbines; process heat HTGR reactors; GCFR reactor thermal hydraulics; and gas cooling of fusion reactors.
Book Synopsis Thermal Design of Nuclear Reactors by : R. H. S. Winterton
Download or read book Thermal Design of Nuclear Reactors written by R. H. S. Winterton and published by Elsevier. This book was released on 2014-04-23 with total page 206 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Design of Nuclear Reactors
Book Synopsis Response of a Helium-Cooled Fast Reactor to Changes in Coolant Flow and Reactivity by :
Download or read book Response of a Helium-Cooled Fast Reactor to Changes in Coolant Flow and Reactivity written by and published by . This book was released on 1967 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis High Temperature Gas-cooled Reactors by : Tetsuaki Takeda
Download or read book High Temperature Gas-cooled Reactors written by Tetsuaki Takeda and published by Academic Press. This book was released on 2021-02-24 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.
Book Synopsis Heat Transfer and Fluid Flow in Nuclear Systems by : Henri Fenech
Download or read book Heat Transfer and Fluid Flow in Nuclear Systems written by Henri Fenech and published by Elsevier. This book was released on 2013-10-22 with total page 591 pages. Available in PDF, EPUB and Kindle. Book excerpt: Heat Transfer and Fluid in Flow Nuclear Systems discusses topics that bridge the gap between the fundamental principles and the designed practices. The book is comprised of six chapters that cover analysis of the predicting thermal-hydraulics performance of large nuclear reactors and associated heat-exchangers or steam generators of various nuclear systems. Chapter 1 tackles the general considerations on thermal design and performance requirements of nuclear reactor cores. The second chapter deals with pressurized subcooled light water systems, and the third chapter covers boiling water reactor systems. Chapter 4 tackles liquid metal cooled systems, while Chapter 5 discusses helium cooled systems. The last chapter deals with heat-exchangers and steam generators. The book will be of great help to engineers, scientists, and graduate students concerned with thermal and hydraulic problems.
Book Synopsis In-pile Heat Transfer Studies of Roughened Helium-cooled Reactor Fuel Elements by :
Download or read book In-pile Heat Transfer Studies of Roughened Helium-cooled Reactor Fuel Elements written by and published by . This book was released on 1967 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Evaluation of High-temperature Gas-cooled Reactors by : Oak Ridge National Laboratory
Download or read book An Evaluation of High-temperature Gas-cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book REPP written by R. M. Hiatt and published by . This book was released on 1969 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: REPP, a digital computer method for designing pressure water and boiling water reactor cores within specified heat transfer and fuel centerline temperature limits is presented. The method incorporates the Westinghouse W-2 and W-3 empirical correlations and a theoretical hot channel model to predict burnout conditions in a rod bundle. Two geometries are considered; rods in a triangular array and rods in a square lattice. The heat transfer problem solved is a one-dimensional analysis. Pressure drop is considered for four types of fuel-pin spacers. Variable heat generation rate through the fuel-pin and sintering in low density fuels are also included.
Book Synopsis A Helium-cooled Blanket Design of the Low Aspect Ratio Reactor by :
Download or read book A Helium-cooled Blanket Design of the Low Aspect Ratio Reactor written by and published by . This book was released on 1998 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can have a major radius as small as 2.9 m resulting in a device with competitive cost of electricity at 49 mill/kWh. One of the technology requirements of this design is a high performance high power density first wall and blanket system. A 15 MPa helium-cooled, V-alloy and stagnant LiPb breeder first wall and blanket design was utilized. Due to the low solubility of tritium in LiPb, there is the concern of tritium migration and the formation of V-hydride. To address these issues, a lithium breeder system with high solubility of tritium has been evaluated. Due to the reduction of blanket energy multiplication to 1.2, to maintain a plant Q of> 4, the major radius of the reactor has to be increased to 3.05 m. The inlet helium coolant temperature is raised to 436 C in order to meet the minimum V-alloy temperature limit everywhere in the first wall and blanket system. To enhance the first wall heat transfer, a swirl tape coolant channel design is used. The corresponding increase in friction factor is also taken into consideration. To reduce the coolant system pressure drop, the helium pressure is increased from 15 to 18 MPa. Thermal structural analysis is performed for a simple tube design. With an inside tube diameter of 1 cm and a wall thickness of 1.5 mm, the lithium breeder can remove an average heat flux and neutron wall loading of 2 and 8 MW/m(2), respectively. This reference design can meet all the temperature and material structural design limits, as well as the coolant velocity limits. Maintaining an outlet coolant temperature of 650 C, one can expect a gross closed cycle gas turbine thermal efficiency of 45%. This study further supports the use of helium coolant for high power density reactor design. When used with the low aspect ratio reactor concept a competitive fusion reactor can be projected at 51.9 mill/kWh.
Author :General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science Publisher : ISBN 13 : Total Pages :246 pages Book Rating :4.3/5 (243 download)
Book Synopsis Design Study Report for TARGET by : General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science
Download or read book Design Study Report for TARGET written by General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science and published by . This book was released on 1964 with total page 246 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Book Synopsis Storage and Hybridization of Nuclear Energy by : Hitesh Bindra
Download or read book Storage and Hybridization of Nuclear Energy written by Hitesh Bindra and published by Academic Press. This book was released on 2018-11-22 with total page 302 pages. Available in PDF, EPUB and Kindle. Book excerpt: Storage and Hybridization of Nuclear Energy: Techno-economic Integration of Renewable and Nuclear Energy provides a unique analysis of the storage and hybridization of nuclear and renewable energy. Editor Bindra and his team of expert contributors present various global methodologies to obtain the techno-economic feasibility of the integration of storage or hybrid cycles in nuclear power plants. Aimed at those studying, researching and working in the nuclear engineering field, this book offers nuclear reactor technology vendors, nuclear utilities workers and regulatory commissioners a very unique resource on how to access reliable, flexible and clean energy from variable-generation. Presents a unique view on the technologies and systems available to integrate renewables and nuclear energy Provides insights into the different methodologies and technologies currently available for the storage of energy Includes case studies from well-known experts working on specific integration concepts around the world
Book Synopsis Super Light Water Reactors and Super Fast Reactors by : Yoshiaki Oka
Download or read book Super Light Water Reactors and Super Fast Reactors written by Yoshiaki Oka and published by Springer Science & Business Media. This book was released on 2010-07-01 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt: Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.
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.
Book Synopsis Balance of Plant Analysis for High Temperature Gas Cooled Reactors by : Chunyun Wang
Download or read book Balance of Plant Analysis for High Temperature Gas Cooled Reactors written by Chunyun Wang and published by LAP Lambert Academic Publishing. This book was released on 2009-09 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt: As a Generation IV nuclear system, the High Temperature Gas Cooled Reactor (HTGR) desires a gas turbine cycle (Brayton cycle) as the power conversion system for it to achieve economic competitiveness. The availability of compact heat exchangers and helium turbo-machinery are thus the critical enabling technology for the gas turbine cycle. This book performs an extensive study on the power conversion system: design constraints, cycle variations, compact heat exchangers, high efficiency helium turbo-machinery and cycle control methods. A detailed steady state and dynamic model is developed for studying the cycle design in terms of efficiency and controllability. An indirect closed helium cycle design is developed in this book by identifying key advances in the technology that could reasonably be expected to be achieved with limited R&D. The modular conceptual design for the intermediate heat exchanger (IHX) and recuperator is also performed.
Book Synopsis Advanced and High-temperature Gas-cooled Reactors by :
Download or read book Advanced and High-temperature Gas-cooled Reactors written by and published by . This book was released on 1969 with total page 942 pages. Available in PDF, EPUB and Kindle. Book excerpt:
