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Thermal Hydraulic Analyses For Coupling High Temperature Gas Cooled Reactor To Hydrogen Plant
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Book Synopsis Thermal Hydraulic Analyses for Coupling High Temperature Gas-Cooled Reactor to Hydrogen Plant by : S. Sherman
Download or read book Thermal Hydraulic Analyses for Coupling High Temperature Gas-Cooled Reactor to Hydrogen Plant written by S. Sherman and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the high-temperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power plant. An intermediate heat transport loop will be required to separate the operations and safety functions of the nuclear and hydrogen plants. A next generation high-temperature reactor could be envisioned as a single-purpose facility that produces hydrogen or a dual-purpose facility that produces hydrogen and electricity. Early plants, such as the proposed Next Generation Nuclear Plant (NGNP), may be dual-purpose facilities that demonstrate both hydrogen and efficient electrical generation. Later plants could be single-purpose facilities. At this stage of development, both single- and dual-purpose facilities need to be understood. A number of possible configurations for a system that transfers heat between the nuclear reactor and the hydrogen and/or electrical generation plants were identified. These configurations included both direct and indirect cycles for the production of electricity. Both helium and liquid salts were considered as the working fluid in the intermediate heat transport loop. Methods were developed toperform thermal-hydraulic and cycle-efficiency evaluations of the different configurations and coolants. The thermal-hydraulic evaluations estimated the sizes of various components in the intermediate heat transport loop for the different configurations. The relative sizes of components provide a relative indication of the capital cost associated with the various configurations. Estimates of the overall cycle efficiency of the various configurations were also determined. The evaluations determined which configurations and coolants are the most promising from thermalhydraulic and efficiency points of view.
Book Synopsis Thermal Hydraulic Analysis of HTGR Coupled with Hydrogen Plant by : Chang Oh
Download or read book Thermal Hydraulic Analysis of HTGR Coupled with Hydrogen Plant written by Chang Oh and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US Department of Energy is investigating the use of high-temperature gas-cooled reactors (HTGR) to produce electricity and hydrogen. Although the hydrogen production processes using the nuclear energy are in an early stage of development, coupling hydrogen plant to HTGR requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear plant. In anticipation of the design, development and procurement of an advanced power conversion system for HTGR, this study was initiated to identify the major design and technology options and their tradeoffs in the evaluation of power conversion system (PCS) coupled to hydrogen plant. In this study, we investigated a number of design configurations and performed thermal hydraulic analyses using various working fluids and various conditions. This paper includes a portion of thermal hydraulic results based on a direct cycle and a parallel intermediate heat exchanger (IHX) configuration option.
Book Synopsis Design Configurations for a Very High Temperature Gas-Cooled Reactor Designed to Generate Electricity and Hydrogen by : Conference preceedings
Download or read book Design Configurations for a Very High Temperature Gas-Cooled Reactor Designed to Generate Electricity and Hydrogen written by Conference preceedings and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The High Temperature Gas-Cooled Reactor is being envisioned that will generate not just electricity, but also hydrogen to charge up fuel cells for cars, trucks and other mobile energy uses. INL engineers studied various heat-transfer working fluids-including helium and liquid salts-in seven different configurations. In computer simulations, serial configurations diverted some energy from the heated fluid flowing to the electric plant and hydrogen production plant. In anticipation of the design, development and procurement of an advanced power conversion system for HTGR, this study was initiated to identify the major design and technology options and their tradeoffs in the evaluation of power conversion system (PCS) coupled to hydrogen plant. In this study, we investigated a number of design configurations and performed thermal hydraulic analyses using various working fluids and various conditions (Oh, 2005). This paper includes a portion of thermal hydraulic results based on a direct cycle and a parallel intermediate heat exchanger (IHX) configuration option.
Book Synopsis Thermal-Hydraulic Analyses of Heat Transfer Fluid Requirements and Characteristics for Coupling A Hydrogen Production Plant to a High-Temperature Nuclear Reactor by : D. F. Wilson
Download or read book Thermal-Hydraulic Analyses of Heat Transfer Fluid Requirements and Characteristics for Coupling A Hydrogen Production Plant to a High-Temperature Nuclear Reactor written by D. F. Wilson and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Department of Energy is investigating the use of high-temperature nuclear reactors to producehydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogenproduction processes are in an early stage of development, coupling either of these processes to the hightemperaturereactor requires both efficient heat transfer and adequate separation of the facilities to assurethat off-normal events in the production facility do not impact the nuclear power plant. An intermediateheat transport loop will be required to separate the operations and safety functions of the nuclear andhydrogen plants. A next generation high-temperature reactor could be envisioned as a single-purposefacility that produces hydrogen or a dual-purpose facility that produces hydrogen and electricity. Earlyplants, such as the proposed Next Generation Nuclear Plant, may be dual-purpose facilities thatdemonstrate both hydrogen and efficient electrical generation. Later plants could be single-purposefacilities. At this stage of development, both single- and dual-purpose facilities need to be understood. Seven possible configurations for a system that transfers heat between the nuclear reactor and thehydrogen and/or electrical generation plants were identified. These configurations included both directand indirect cycles for the production of electricity. Both helium and liquid salts were considered as theworking fluid in the intermediate heat transport loop. Methods were developed to perform thermalhydraulicand cycle-efficiency evaluations of the different configurations and coolants. The thermalhydraulicevaluations estimated the sizes of various components in the intermediate heat transport loopfor the different configurations. The relative sizes of components provide a relative indication of thecapital cost associated with the various configurations. Estimates of the overall cycle efficiency of thevarious configurations were also determined. The evaluations determined which configurations andcoolants are the most promising from thermal-hydraulic and efficiency points of view. These evaluationsalso determined which configurations and options do not appear to be feasible at the current time.
Book Synopsis POWER CYCLE AND STRESS ANALYSES FOR HIGH TEMPERATURE GAS-COOLED REACTOR. by :
Download or read book POWER CYCLE AND STRESS ANALYSES FOR HIGH TEMPERATURE GAS-COOLED REACTOR. written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Department of Energy and the Idaho National Laboratory are developing a Next Generation Nuclear Plant (NGNP) to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold 1) efficient low cost energy generation and 2) hydrogen production. Although a next generation plant could be developed as a single-purpose facility, early designs are expected to be dual-purpose. While hydrogen production and advanced energy cycles are still in its early stages of development, research towards coupling a high temperature reactor, electrical generation and hydrogen production is under way. Many aspects of the NGNP must be researched and developed in order to make recommendations on the final design of the plant. Parameters such as working conditions, cycle components, working fluids, and power conversion unit configurations must be understood. Three configurations of the power conversion unit were demonstrated in this study. A three-shaft design with three turbines and four compressors, a combined cycle with a Brayton top cycle and a Rankine bottoming cycle, and a reheated cycle with three stages of reheat were investigated. An intermediate heat transport loop for transporting process heat to a High Temperature Steam Electrolysis (HTSE) hydrogen production plant was used. Helium, CO2, and a 80% nitrogen, 20% helium mixture (by weight) were studied to determine the best working fluid in terms cycle efficiency and development cost. In each of these configurations the relative component size were estimated for the different working fluids. The relative size of the turbomachinery was measured by comparing the power input/output of the component. For heat exchangers the volume was computed and compared. Parametric studies away from the baseline values of the three-shaft and combined cycles were performed to determine the effect of varying conditions in the cycle. This gives some insight into the sensitivity of these cycles to various operating conditions as well as trade offs between efficiency and capital cost. Parametric studies were carried out on reactor outlet temperature, mass flow, pressure, and turbine cooling. Recommendations on the optimal working fluid for each configuration were made. Engineering analyses were performed for several configurations of the intermediate heat transport loop that transfers heat from the nuclear reactor to the hydrogen production plant. The analyses evaluated parallel and concentric piping arrangements and two different working fluids, including helium and a liquid salt. The thermal-hydraulic analyses determined the size and insulation requirements for the hot and cold leg pipes in the different configurations. Mechanical analyses were performed to determine hoop stresses and thermal expansion characteristics for the different configurations. Economic analyses were performed to estimate the cost of the various configurations.
Book Synopsis Neutronic and Thermal-hydraulic Coupling Study on High Temperature Gas-cooled Reactor by : Cheng-Kai Tai
Download or read book Neutronic and Thermal-hydraulic Coupling Study on High Temperature Gas-cooled Reactor written by Cheng-Kai Tai and published by . This book was released on 2017 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Hydraulic Analysis of a Reduced Scale High Temperature Gas-Cooled Reactor Test Facility and Its Prototype with MELCOR by : Bradley Aaron Beeny
Download or read book Thermal Hydraulic Analysis of a Reduced Scale High Temperature Gas-Cooled Reactor Test Facility and Its Prototype with MELCOR written by Bradley Aaron Beeny and published by . This book was released on 2013 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pursuant to the energy policy act of 2005, the High Temperature Gas-Cooled Reactor (HTGR) has been selected as the Very High Temperature Reactor (VHTR) that will become the Next Generation Nuclear Plant (NGNP). Although plans to build a demonstration plant at Idaho National Laboratories (INL) are currently on hold, a cooperative agreement on HTGR research between the U.S. Nuclear Regulatory Commission (NRC) and several academic investigators remains in place. One component of this agreement relates to validation of systems-level computer code modeling capabilities in anticipation of the eventual need to perform HTGR licensing analyses. Because the NRC has used MELCOR for LWR licensing in the past and because MELCOR was recently updated to include gas-cooled reactor physics models, MELCOR is among the system codes of interest in the cooperative agreement. The impetus for this thesis was a code-to-experiment validation study wherein MELCOR computer code predictions were to be benchmarked against experimental data from a reduced-scale HTGR testing apparatus called the High Temperature Test Facility (HTTF). For various reasons, HTTF data is not yet available from facility designers at Oregon State University, and hence the scope of this thesis was narrowed to include only computational studies of the HTTF and its prototype, General Atomics' Modular High Temperature Gas-Cooled Reactor (MHTGR). Using the most complete literature references available for MHTGR design and using preliminary design information on the HTTF, MELCOR input decks for both systems were developed. Normal and off-normal system operating conditions were modeled via implementation of appropriate boundary and inititial conditions. MELCOR Predictions of system response for steady-state, pressurized conduction cool-down (PCC), and depressurized conduction cool-down (DCC) conditions were checked against nominal design parameters, physical intuition, and some computational results available from previous RELAP5-3D analyses at INL. All MELCOR input decks were successfully built and all scenarios were successfully modeled under certain assumptions. Given that the HTTF input deck is preliminary and was based on dated references, the results were altogether imperfect but encouraging since no indications of as yet unknown deficiencies in MELCOR modeling capability were observed. Researchers at TAMU are in a good position to revise the MELCOR models upon receipt of new information and to move forward with MELCOR-to-HTTF benchmarking when and if test data becomes available. The electronic version of this dissertation is accessible from http://hdl.handle.net/1969.1/148182
Book Synopsis Nuclear Energy for Hydrogen Generation through Intermediate Heat Exchangers by : Bahman Zohuri
Download or read book Nuclear Energy for Hydrogen Generation through Intermediate Heat Exchangers written by Bahman Zohuri and published by Springer. This book was released on 2016-07-15 with total page 421 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes recent technological developments in next generation nuclear reactors that have created renewed interest in nuclear process heat for industrial applications. The author’s discussion mirrors the industry’s emerging focus on combined cycle Next Generation Nuclear Plants’ (NGNP) seemingly natural fit in producing electricity and process heat for hydrogen production. To utilize this process heat, engineers must uncover a thermal device that can transfer the thermal energy from the NGNP to the hydrogen plant in the most performance efficient and cost effective way possible. This book is written around that vital quest, and the author describes the usefulness of the Intermediate Heat Exchanger (IHX) as a possible solution. The option to transfer heat and thermal energy via a single-phase forced convection loop where fluid is mechanically pumped between the heat exchangers at the nuclear and hydrogen plants is presented, and challenges associated with this tactic are discussed. As a second option, heat pipes and thermosyphons, with their ability to transport very large quantities of heat over relatively long distance with small temperature losses, are also examined.
Book Synopsis Hydrogen Production from Nuclear Energy by : Greg F Naterer
Download or read book Hydrogen Production from Nuclear Energy written by Greg F Naterer and published by Springer Science & Business Media. This book was released on 2013-03-28 with total page 506 pages. Available in PDF, EPUB and Kindle. Book excerpt: With the resurgence of nuclear power around the world, and the increasingly important role of hydrogen as a clean energy carrier, the utilization of nuclear energy for large-scale hydrogen production will have a key role in a sustainable energy future. Co-generation of both electricity and hydrogen from nuclear plants will become increasingly attractive. It enables load leveling together with renewable energy and storage of electricity in the form of hydrogen, when electricity prices and demand are lowest at off-peak hours of nuclear plants, such as overnight. Hydrogen Production from Nuclear Energy provides an overview of the latest developments and methods of nuclear based hydrogen production, including electrolysis and thermochemical cycles. Particular focus is given to thermochemical water splitting by the copper-chlorine and sulphur-based cycles. Cycle configurations, equipment design, modeling and implementation issues are presented and discussed. The book provides the reader with an overview of the key enabling technologies towards the design and industrialization of hydrogen plants that are co-located and linked with nuclear plants in the future. The book includes illustrations of technology developments, tables that summarize key features and results, overviews of recent advances and new methods of nuclear hydrogen production. The latest results from leading authorities in the fields will be presented, including efficiencies, costs, equipment design, and modeling.
Book Synopsis Thermal-Hydraulic Analysis of Nuclear Reactors by : Bahman Zohuri
Download or read book Thermal-Hydraulic Analysis of Nuclear Reactors written by Bahman Zohuri and published by Springer. This book was released on 2017-05-23 with total page 845 pages. Available in PDF, EPUB and Kindle. Book excerpt: This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.
Download or read book Hydrogen Energy written by Bahman Zohuri and published by Springer. This book was released on 2018-08-25 with total page 293 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes the challenges and solutions the energy sector faces by shifting towards a hydrogen based fuel economy. The most current and up-to-date efforts of countries and leaders in the automotive sector are reviewed as they strive to develop technology and find solutions to production, storage, and distribution challenges. Hydrogen fuel is a zero-emission fuel when burned with oxygen and is often used with electrochemical cells, or combustion in internal engines, to power vehicles and electric devices. This book offers unique solutions to integrating renewable sources of energy like wind or solar power into the production of hydrogen fuel, making it a cost effective, efficient and truly renewable alternative fuel.
Download or read book HEXEREI written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A description is given of the development and verification of a generalized coupled conduction-convection, multichannel heat transfer computer program to analyze specific safety questions involving high temperature gas-cooled reactors (HTGR). The HEXEREI code was designed to provide steady-state and transient heat transfer analysis of the HTGR active core using a basic hexagonal mesh and multichannel coolant flow. In addition, the core auxiliary cooling systems were included in the code to provide more complete analysis of the reactor system during accidents involving reactor trip and cooling down on the auxiliary systems. Included are brief descriptions of the components of the HEXEREI code and sample HEXEREI analyses compared with analytical solutions and other heat transfer codes.
Book Synopsis Nuclear Thermal Hydraulic and Two-Phase Flow by : Jun Wang
Download or read book Nuclear Thermal Hydraulic and Two-Phase Flow written by Jun Wang and published by Frontiers Media SA. This book was released on 2018-10-11 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.
Download or read book HEXERE12 written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: HEXERE12 code development has provided a complex computer code, which is capable of analyzing High Temperature Gas-Cooled Reactors (HTGR) during accidents and providing most of the information necessary for HTGR Safety Studies. HEXERE12 is designed to solve steady-state and transient three-dimensional heat conduction, coupled with convection to axially flowing coolant in a large number of parallel channels. Both the coolant temperature and flow distribution among the channels are influenced by the heat transferred into coolant. The thermal conductivity, density, and specific heat may be spatially and temperature dependent and may further be modified by HTGR design parameters. The conductivity can be anisotropic. Heat generation rates may be dependent on time, position, and HTGR design parameters. The boundary temperatures may be time-dependent. The boundary conditions may be fixed temperatures or any combination of prescribed heat flux, forced convection, and radiation from a surface to a boundary temperature. The boundary condition parameters may be time- and/or temperature-dependent. HEXERE12 can model a coolant which can be helium, air, or a helium-air mixture.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 852 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal-hydraulic Analysis of Gas-cooled Reactor Core Flows by : Amir Keshmiri
Download or read book Thermal-hydraulic Analysis of Gas-cooled Reactor Core Flows written by Amir Keshmiri and published by . This book was released on 2010 with total page 382 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 920 pages. Available in PDF, EPUB and Kindle. Book excerpt:
