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Author : L. Davidson
Publisher :
ISBN 13 :
Total Pages : 152 pages
Book Rating : 4.3/5 (91 download)
Download or read book Design of an Experimental Reactor for High Operating Temperatures written by L. Davidson and published by . This book was released on 1956 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Tetsuaki Takeda
Publisher : Academic Press
ISBN 13 : 012821032X
Total Pages : 478 pages
Book Rating : 4.1/5 (282 download)
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.
Author : Luigi Massimo
Publisher : Elsevier
ISBN 13 : 1483280284
Total Pages : 249 pages
Book Rating : 4.4/5 (832 download)
Download or read book Physics of High-Temperature Reactors written by Luigi Massimo and published by Elsevier. This book was released on 2013-10-22 with total page 249 pages. Available in PDF, EPUB and Kindle. Book excerpt: Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
Author : Sai K. Mylavarapu
Publisher :
ISBN 13 :
Total Pages : 110 pages
Book Rating : 4.:/5 (289 download)
Download or read book Development of Compact Heat Exchangers for Very High-temperature Gas-cooled Reactors written by Sai K. Mylavarapu and published by . This book was released on 2008 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: The U.S. Department of Energy's Generation IV Program has generated considerable interest for High-Temperature Gas-Cooled Reactors (HTGR), in particular, the Very-High-Temperature Reactor (VHTR). VHTR is one of the six reactor concepts selected by the Generation IV International Forum and is anticipated to be reactor type for the Next Generation Nuclear Plant (NGNP). The VHTR concept, with a projected plant design service life of 60 years, is being actively researched not only due to its near-term deployment potential but also because it offers a broad range of process heat applications ranging from electricity generation to hydrogen co-generation. To efficiently and reliably transfer the thermal output from the reactor core, VHTRs require high temperature (900-950 0C) and high integrity heat exchangers with high effectiveness during normal and off-normal conditions. A class of compact plate-type heat exchangers, namely, Printed Circuit Heat Exchangers (PCHEs), made of high-temperature materials and found to have these above characteristics are being increasingly pursued for heavy duty applications. The current thesis work is a part of a larger research project aimed at investigating the design, fabrication, testing, modeling, and optimization of PCHEs at operating temperatures proposed to be realized in VHTRs. In the present work, two PCHEs were designed and fabricated. In addition, a detailed design of a high-temperature helium test facility to test the thermal-hydraulic performance of these PCHEs was completed. Owing to the high operating temperatures and pressures, a detailed investigation on various high-temperature materials was carried out to aid in the design of the test facility and the heat exchangers. The study showed that Alloys 617 and 230 are the leading candidate materials for high-temperature applications. However, economics and material availability in the required form dictated the final design operating conditions. The helium test facility is of Alloy 800HT construction and is currently being constructed at The Ohio State University. It is intended to facilitate experiments at operating temperatures and pressures up to 900 0C and 3 MPa, respectively. Two PCHEs, each having 10 hot and 10 cold plates with 12 channels in each plate, were fabricated using Alloy 617 plates. In addition, the processes related to the fabrication of PCHEs, namely photochemical machining and diffusion bonding techniques were investigated and successfully established for Alloy 617 plates. The PCHEs will be tested in the helium test facility for their heat transfer and pressure drop characteristics at various operating temperatures and pressures. The experimental database generated from the test facility will then be used for model development and computer code validation. In summary, the current thesis focuses on the study of the high-temperature materials, design of the helium test facility, design, development, and fabrication of the high-temperature PCHEs.
Download or read book 40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959 written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC2- UC2 particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results indicated that the central fuel-element temperatures must not exceed 2300-C for routine operation. An important start was made in developing an understanding of how to treat the neutron thermalization process in high-temperature graphite reactors. Analytical techniques for calculating the thermal neutron spectra in poisoned graphite media were developed and programmed for the IBM 704 computer. The experimental technique of measuring neutron spectra by using a pulsed linear electron accelerator was demonstrated by measurements made with boron-loaded graphite. A mockup of a small portion of the reactor core was constructed and operated to determine the local heat-transfer coefficients and pressure drop in the tricusp- shaped coolant passage. Initial results indicated that the variation of the heat-transfer coefficient around the circumference of the element is less than expected. Studies were started of the transient temperatures and stresses developed in the pressure vessel as a result of load changes or a scram. A detailed study of several types of steam generator for use in the nuclear steam supply system was completed. A design incorporating a steam drum was selected for further study. Preliminary flow diagrams were completed for the helium- purification and fission-product trapping systems. Adsorption isobars for selected fission products in activated carbon were measured and will be used in the detailed design of the trapping system. Detailed planning of the experimental reactor physics program was initiated. Progress was made in the identification of the principal safeguards problems for this type of reactor, and a preliminary safety analysis of the plant was completed. (auth).
Author : U.S. Atomic Energy Commission. Technical Information Service
Publisher :
ISBN 13 :
Total Pages : 52 pages
Book Rating : 4.3/5 (91 download)
Download or read book Experimental Reactors written by U.S. Atomic Energy Commission. Technical Information Service and published by . This book was released on 1956 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Pascal Yvon
Publisher : Woodhead Publishing
ISBN 13 : 0081009127
Total Pages : 686 pages
Book Rating : 4.0/5 (81 download)
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
Author : International Atomic Energy Agency
Publisher :
ISBN 13 : 9789201253101
Total Pages : 639 pages
Book Rating : 4.2/5 (531 download)
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.
Author : L. E. Fromm
Publisher :
ISBN 13 :
Total Pages : 30 pages
Book Rating : 4.:/5 (319 download)
Download or read book Decomposition of Water at High Temperatures and Pressures Under Reactor Irradiation written by L. E. Fromm and published by . This book was released on 1956 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: The investigation of the high temperature and pressure dissociation of water under irradiation was undertaken by the Power Pile Division of Oak Ridge National Laboratory in an effort to determine the degree of importance of the phenomenon with respect to the design of a high temperature water cooled power reactor. Theory and past experimentation indicate that net steady state dissociation is determined by the rates of the dissociation and recombination reactions under the imposed conditions, the dissociation rate being essentially a function of flux and the recombination rate essentially a function of temperature. A static electrically heated autoclave and associated temperature controlling, pressure recording, filling, purging and sampling apparatus was constructed and the autoclave installed in a test hole of the X-10 reactor under an approximate thermal flux of 5 x 10(exp 11) neutron/cm2 - sec. Two data runs were made, one at 3500 F and one at 4500 F, on water with a gas phase of saturated steam. Neither run showed any significant increase in pressure throughout, and analyses of the water phase indicated very slight gas formation easily attributed to autoclave corrosion. The conclusion was reached that, under the conditions of flux and temperature of these experiments, the recombination rate is considerably higher than the dissociation rate. Several attempts were made to determine whether or not gaseous hydrogen and oxygen added to the gas phase would dissolve and enter into the recombination reaction, but inconsistent leaks in the system valving developed, rendering the data worthless. At present the valving is being rebuilt, and these experiments will be repeated.
Author : Kurt Kugeler
Publisher : Springer
ISBN 13 : 3662577127
Total Pages : 903 pages
Book Rating : 4.6/5 (625 download)
Download or read book Modular High-temperature Gas-cooled Reactor Power Plant written by Kurt Kugeler and published by Springer. This book was released on 2018-10-05 with total page 903 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Modular High-temperature Gas-cooled Reactor Power Plant" introduces the power plants driven by modular high temperature gas-cooled reactors (HTR), which are characterized by their inherent safety features and high output temperatures. HTRs have the potential to be adopted near demand side to supply both electricity and process heat, directly replacing conventional fossil fuels. The world is confronted with two dilemmas in the energy sector, namely climate change and energy supply security. HTRs have the potential to significantly alleviate these concerns. This book will provide readers with a thorough understanding of HTRs, their history, principles, and fields of application. The book is intended for researchers and engineers involved with nuclear engineering and energy technology.
Author : Neil Rutger Taylor
Publisher :
ISBN 13 :
Total Pages : 89 pages
Book Rating : 4.:/5 (15 download)
Download or read book Analysis of a High Temperature Fission Chamber Experiment for Next Generation written by Neil Rutger Taylor and published by . This book was released on 2017 with total page 89 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission chambers are a vital instrument for the power monitoring of nuclear reactors, and as the current generation of reactors age, the need for next generation reactors to come online grows. Along with these new reactors, sensors and instruments are required for safe operation. One such instrument is a fission chamber capable of surviving the elevated temperatures and harsh environments that come with the next fleet of reactors. A high temperature fission chamber (HTFC) was designed in collaboration with Oak Ridge National Lab to fill this demand for new technology. This design was modeled using MCNP6 and an experiment was conducted at the Ohio State University Research Reactor to test the measurement capabilities of the design. MCNP6 was utilized to simulate expected fission rates from the HTFC at a variety of power levels and locations around the OSURR. These results were then used to create a reactor test plan utilizing the different locations and power levels to test the operation of the HTFC in both pulse and current mode operation. Along with these simulations, a detailed activation analysis utilizing the ORIGEN module within SCALE 6.1 was performed to determine the expected activity level and dose rates associated with the reactor experiment. A gas sampling system was developed to sample gas flowed through the experimental apparatus to ensure that the HTFC survived the experiment. This sampling system monitored the flow gas for alpha and beta radiation from fission products that would have leaked out of the containment in case of failure.
Author : U.S. Atomic Energy Commission
Publisher :
ISBN 13 :
Total Pages : 386 pages
Book Rating : 4.:/5 (37 download)
Download or read book Civilian Power Reactor Program: Addendum. Core parameter studies for selected reactor types written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 386 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. H. S. Winterton
Publisher : Pergamon
ISBN 13 :
Total Pages : 212 pages
Book Rating : 4.:/5 (41 download)
Download or read book Thermal Design of Nuclear Reactors written by R. H. S. Winterton and published by Pergamon. This book was released on 1981 with total page 212 pages. Available in PDF, EPUB and Kindle. Book excerpt: Of reactor physics -- Reactor systems -- Fuel-road design -- Forced-convection heat transfer -- Boiling heat transfer -- Fluid flow -- Safety analysis -- Core thermohydraulic design -- Steam cycles -- Fusion reactors -- Temperature distribution following sudden total loss of cooling -- Properties of coolants -- Conversion factors -- Answers to selected problems.
Author : Mark David DeHart
Publisher : Frontiers Media SA
ISBN 13 : 283253094X
Total Pages : 146 pages
Book Rating : 4.8/5 (325 download)
Download or read book Benchmark Experiments, Development and Needs in Support of Advanced Reactor Design written by Mark David DeHart and published by Frontiers Media SA. This book was released on 2023-08-01 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.3/5 (91 download)
Download or read book The Oak Ridge High Flux Isotope Reactor, Design and Initial Operation written by and published by . This book was released on 1966 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Karl Verfondern
Publisher : Forschungszentrum Jülich
ISBN 13 : 3893364684
Total Pages : 199 pages
Book Rating : 4.8/5 (933 download)
Download or read book Nuclear Energy for Hydrogen Production written by Karl Verfondern and published by Forschungszentrum Jülich. This book was released on 2007 with total page 199 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : U.S. Atomic Energy Commission
Publisher :
ISBN 13 :
Total Pages : 98 pages
Book Rating : 4.3/5 (243 download)
Download or read book Civilian Power Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 98 pages. Available in PDF, EPUB and Kindle. Book excerpt:
