Design Modification for the Modular Helium Reactor for Higher Temperature Operation and Reliability Studies for Nuclear Hydrogen Production Processes

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Book Synopsis Design Modification for the Modular Helium Reactor for Higher Temperature Operation and Reliability Studies for Nuclear Hydrogen Production Processes by : S. M. Mohsin Reza

Download or read book Design Modification for the Modular Helium Reactor for Higher Temperature Operation and Reliability Studies for Nuclear Hydrogen Production Processes written by S. M. Mohsin Reza and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Design options have been evaluated for the Modular Helium Reactor (MHR) for higher temperature operation. An alternative configuration for the MHR coolant inlet flow path is developed to reduce the peak vessel temperature (PVT). The coolant inlet path is shifted from the annular path between reactor core barrel and vessel wall through the permanent side reflector (PSR). The number and dimensions of coolant holes are varied to optimize the pressure drop, the inlet velocity, and the percentage of graphite removed from the PSR to create this inlet path. With the removal of ~10% of the graphite from PSR the PVT is reduced from 541 0C to 421 0C. A new design for the graphite block core has been evaluated and optimized to reduce the inlet coolant temperature with the aim of further reduction of PVT. The dimensions and number of fuel rods and coolant holes, and the triangular pitch have been changed and optimized. Different packing fractions for the new core design have been used to conserve the number of fuel particles. Thermal properties for the fuel elements are calculated and incorporated into these analyses. The inlet temperature, mass flow and bypass flow are optimized to limit the peak fuel temperature (PFT) within an acceptable range. Using both of these modifications together, the PVT is reduced to ~350 0C while keeping the outlet temperature at 950 0C and maintaining the PFT within acceptable limits. The vessel and fuel temperatures during low pressure conduction cooldown and high pressure conduction cooldown transients are found to be well below the design limits. The reliability and availability studies for coupled nuclear hydrogen production processes based on the sulfur iodine thermochemical process and high temperature electrolysis process have been accomplished. The fault tree models for both these processes are developed. Using information obtained on system configuration, component failure probability, component repair time and system operating modes and conditions, the system reliability and availability are assessed. Required redundancies are made to improve system reliability and to optimize the plant design for economic performance. The failure rates and outage factors of both processes are found to be well below the maximum acceptable range.

Hydrogen Production Using the Modular Helium Reactor

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Total Pages : pages
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Book Synopsis Hydrogen Production Using the Modular Helium Reactor by : M. Richards

Download or read book Hydrogen Production Using the Modular Helium Reactor written by M. Richards and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The high-temperature characteristics of the Modular Helium Reactor (MHR) make it a strong candidate for the production of hydrogen using either thermochemical or high-temperature electrolysis (HTE) processes. Using heat from the MHR to drive a Sulfur-Iodine (S-I) thermochemical hydrogen process has been the subject of a DOE sponsored Nuclear Engineering Research Initiative (NERI) project lead by General Atomics, with participation from the Idaho National Engineering and Environmental Laboratory (INEEL) and Texas A & M University. While the focus of much of the initial work was on the S-I thermochemical production of hydrogen, recent activities have also included development of a preconceptual design for an integral HTE hydrogen production plant driven by the process heat and electricity produced by a 600 MWt MHR. This paper describes RELAP5-3D analyses performed to evaluate alternative primary system cooling configurations for the MHR to minimize peak reactor vessel and core temperatures while achieving core helium outlet temperatures in the range of 900 oC to 1000 oC, needed for the efficient production of hydrogen using either the S-I thermochemical or HTE process. The cooling schemes investigated are intended to ensure peak fuel temperatures do not exceed specified limits under normal or transient upset conditions, and that reactor vessel temperatures do not exceed ASME code limits for steady-state or transient conditions using standard LWR vessel materials. Preconceptual designs for both an S-I thermochemical and HTE hydrogen production plant driven by a 600 MWt MHR at helium outlet temperatures in the range of 900 oC to 1000 oC are described and compared. An initial SAPHIRE model to evaluate the reliability, maintainablility, and availability of the S-I hydrogen production plant is also discussed, and plans for future assessments of conceptual designs for both a S-I thermochemical and HTE hydrogen production plant coupled to a 600 MWt modular helium reactor are described.

Cong weibo dao guang

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (695 download)

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Book Synopsis Cong weibo dao guang by :

Download or read book Cong weibo dao guang written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

USE OF THE MODULAR HELIUM REACTOR FOR HYDROGEN PRODUCTION.

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ISBN 13 :
Total Pages : 12 pages
Book Rating : 4.:/5 (316 download)

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Book Synopsis USE OF THE MODULAR HELIUM REACTOR FOR HYDROGEN PRODUCTION. by : KR. SCHULTZ

Download or read book USE OF THE MODULAR HELIUM REACTOR FOR HYDROGEN PRODUCTION. written by KR. SCHULTZ and published by . This book was released on 2003 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: OAK-B135 A significant ''Hydrogen Economy'' is predicted that will reduce our dependence on petroleum imports and reduce pollution and greenhouse gas emissions. Hydrogen is an environmentally attractive fuel that has the potential to displace fossil fuels, but contemporary hydrogen production is primarily based on fossil fuels. The author has recently completed a three-year project for the US Department of Energy (DOE) whose objective was to ''define an economically feasible concept for production of hydrogen, using an advanced high-temperature nuclear reactor as the energy source''. Thermochemical water-slitting, a chemical process that accomplishes the decomposition of water into hydrogen and oxygen, met this objective. The goal of the first phase of this study was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen, and to select one for further detailed consideration. They selected the Sulfur-Iodine cycle. In the second phase, they reviewed all the basic reactor types for suitability to provide the high temperature heat needed by the selected thermochemical water splitting cycle and chose the helium gas-cooled reactor. In the third phase they designed the chemical flowsheet for the thermochemical process and estimated the efficiency and cost of the process and the projected cost of producing hydrogen. These results are summarized in this report.

Analysis of Reference Design for Nuclear-Assisted Hydrogen Production at 750°C Reactor Outlet Temperature

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

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Book Synopsis Analysis of Reference Design for Nuclear-Assisted Hydrogen Production at 750°C Reactor Outlet Temperature by :

Download or read book Analysis of Reference Design for Nuclear-Assisted Hydrogen Production at 750°C Reactor Outlet Temperature written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The use of High Temperature Electrolysis (HTE) for the efficient production of hydrogen without the greenhouse gas emissions associated with conventional fossil-fuel hydrogen production techniques has been under investigation at the Idaho National Engineering Laboratory (INL) for the last several years. The activities at the INL have included the development, testing and analysis of large numbers of solid oxide electrolysis cells, and the analyses of potential plant designs for large scale production of hydrogen using a high-temperature gas-cooled reactor (HTGR) to provide the process heat and electricity to drive the electrolysis process. The results of this research led to the selection in 2009 of HTE as the preferred concept in the U.S. Department of Energy (DOE) hydrogen technology down-selection process. However, the down-selection process, along with continued technical assessments at the INL, has resulted in a number of proposed modifications and refinements to improve the original INL reference HTE design. These modifications include changes in plant configuration, operating conditions and individual component designs. This report describes the resulting new INL reference design coupled to two alternative HTGR power conversion systems, a Steam Rankine Cycle and a Combined Cycle (a Helium Brayton Cycle with a Steam Rankine Bottoming Cycle). Results of system analyses performed to optimize the design and to determine required plant performance and operating conditions when coupled to the two different power cycles are also presented. A 600 MWt high temperature gas reactor coupled with a Rankine steam power cycle at a thermal efficiency of 44.4% can produce 1.85 kg/s of hydrogen and 14.6 kg/s of oxygen. The same capacity reactor coupled with a combined cycle at a thermal efficiency of 42.5% can produce 1.78 kg/s of hydrogen and 14.0 kg/s of oxygen.

Advanced Intermediate Heat Transport Loop Design Configurations for Hydrogen Production Using High Temperature Nuclear Reactors

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)

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Book Synopsis Advanced Intermediate Heat Transport Loop Design Configurations for Hydrogen Production Using High Temperature Nuclear Reactors by : Chang Oh

Download or read book Advanced Intermediate Heat Transport Loop Design Configurations for Hydrogen Production Using High Temperature Nuclear Reactors written by Chang Oh and published by . This book was released on 2005 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 to perform thermal-hydraulic evaluations 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 thermal-hydraulic and efficiency points of view.

Prismatic Modular Reactor Analysis with Melcor

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Publisher : LAP Lambert Academic Publishing
ISBN 13 : 9783844312263
Total Pages : 404 pages
Book Rating : 4.3/5 (122 download)

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Book Synopsis Prismatic Modular Reactor Analysis with Melcor by : Ni Zhen

Download or read book Prismatic Modular Reactor Analysis with Melcor written by Ni Zhen and published by LAP Lambert Academic Publishing. This book was released on 2011-03 with total page 404 pages. Available in PDF, EPUB and Kindle. Book excerpt: Hydrogen, a more sustainable source of energy, is a potential substitute for hydrocarbon fuel for power generation. The Very High Temperature gas-cooled Reactor (VHTR) concept can produce hydrogen with high efficiency and in large quantities. The US Department of Energy plans to build a VHTR as a next-generation hydrogen/electricity production plant. This reactor concept is very different from that of commercial reactors in the US. In order to acquire licensing eligibility for VHTRs, analysis tools need to be validated and applied to design and evaluate VHTRs under operation conditions and accident scenarios. In this thesis, MELCOR, a severe accident code, was used to analyze one of the VHTR designs - a prismatic core Next Generation Nuclear Plant (NGNP). The NGNP is based on General Atomics' (GA) Gas Turbine - Modular Helium Reactor (GT-MHR) 600 MW design. According to the current literature survey, more data is available for the GT-MHR than for the NGNP. Therefore, for the purposes of extending MELCOR capabilities and code validation, a model of the GT-MHR reactor pressure vessel (RPV) was developed. Based on the currently available data, a model of the NGNP RPV was then developed through modifying the GT-MHR RPV model. For both RPV models, coolant outlet temperature under normal operating conditions corresponds well to the data from literature. The reactor cavity cooling systems (RCCS), which passively removes heat from the RPV wall to the outside atmosphere, was then added to this GT-MHR RPV model. With this model addition, the heat removal rate of the RCCS under normal operating conditions was calculated to correspond well to the data from references. Pressurized conduction cooldown (PCC), one of the important postulated accident scenarios for a prismatic core reactor, was simulated with the complete model. MELCOR has been demonstrated to have the ability of modeling a prismatic core VHTR. The calculated outlet temperature and mass flow rate under normal operation correspond well to references. However, the calculation for the heat distribution in the graphite and fuel is unsatisfactory which requires MELCOR modification for the PCC simulation. For future work, a complete model of the NGNP under normal operation conditions will be developed when additional data becomes available.

The Modular Helium Reactor for Hydrogen Production

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)

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Book Synopsis The Modular Helium Reactor for Hydrogen Production by : L. Brown

Download or read book The Modular Helium Reactor for Hydrogen Production written by L. Brown and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: For electricity and hydrogen production, an advanced reactor technology receiving considerable international interest is a modular, passively-safe version of the high-temperature, gas-cooled reactor (HTGR), known in the U.S. as the Modular Helium Reactor (MHR), which operates at a power level of 600 MW(t). For hydrogen production, the concept is referred to as the H2-MHR. Two concepts that make direct use of the MHR high-temperature process heat are being investigated in order to improve the efficiency and economics of hydrogen production. The first concept involves coupling the MHR to the Sulfur-Iodine (SI) thermochemical water splitting process and is referred to as the SI-Based H2-MHR. The second concept involves coupling the MHR to high-temperature electrolysis (HTE) and is referred to as the HTE-Based H2-MHR.

Design of an Experimental Reactor for High Operating Temperatures

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ISBN 13 :
Total Pages : 152 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Design of an Experimental Reactor for High Operating Temperatures by : L. Davidson

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:

Advances in High Temperature Gas Cooled Reactor Fuel Technology

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

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

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

Energy Research Abstracts

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ISBN 13 :
Total Pages : 922 pages
Book Rating : 4.3/5 (129 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 922 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Conceptual Design, Analysis and Optimization of Nuclear-based Hydrogen Production Via Copper-chlorine Thermochemical Cycles

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (755 download)

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Book Synopsis Conceptual Design, Analysis and Optimization of Nuclear-based Hydrogen Production Via Copper-chlorine Thermochemical Cycles by : Mehmet Fatih Orhan

Download or read book Conceptual Design, Analysis and Optimization of Nuclear-based Hydrogen Production Via Copper-chlorine Thermochemical Cycles written by Mehmet Fatih Orhan and published by . This book was released on 2011 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The world faces problems with depleting energy resources and the harmful impact of present energy consumption patterns on the environment, and consequently on the global climate and humanity. The concerns regarding global climate change are serious and have resulted in extensive research and developments on alternative, clean energy sources. While many of the available natural energy resources are limited due to their reliability, quality, quantity and density; nuclear energy has the potential to contribute a significant share of large scale energy supply without or little contributing to climate change. Hydrogen production via thermochemical water decomposition is one of the key potential processes for direct utilization of nuclear thermal energy. Thermochemical water splitting with a copper-chlorine (Cu-Cl) cycle is a promising process that could be linked with nuclear reactors to decompose water into its constituents, oxygen and hydrogen as a net result, through intermediate copper and chlorine compounds with a net input of water and heat. The process involves a series of closed-loop chemical reactions that does not contribute to any greenhouse gas emissions into the environment. Although some preliminary technical studies of the Cu-Cl cycle have been reported and some small lab scale experiments of individual reactions in the cycle have been carried out, there is still a need to link all the sub-steps of the cycle and build a pilot plant, to facilitate eventual commercialization. Such an experimental set up of overall cycle is lacking, especially to evaluate characteristics of the complete cycle such as energy, exergy and cost effectiveness. Simulation packages, such as Aspen Plus, are useful tools to provide the system designer or operator with design, optimization and operation information before building a pilot plant. In this thesis, process analysis is performed and simulation models are developed using the Aspen Plus simulation package, based on experimental work carried out at the University of Ontario Institute of Technology (UOIT), the Argonne National Laboratory (ANL), the Atomic Energy of Canada Limited (AECL) and other sources. The energy and mass balances, stream flows and properties, the heat exchanger duties and shaft work are calculated. Heat recovery options are assessed to improve thermal management and hence overall efficiency of the Cu-Cl cycle. An integrated heat exchange network is designed to use heat from the process streams efficiently and decrease the external heat demand. The efficiency of the process, based on three, four and five-step cycles, is examined in this thesis. The thermal efficiency of the five-step thermochemical process is calculated as 44%, of the four-step process is 43% and of the three-step process is 41%, based on the lower heating value of hydrogen. Sensitivity analyses are performed to study the effects of various operating parameters on the efficiency, yield, and cost. A parametric study is conducted, and possible efficiency improvements are discussed. The manner is investigated in which exergy-related parameters can be used to minimize the cost of a Cu-Cl thermochemical cycle for hydrogen production. The iterative optimization technique presented requires a minimum of available data and provides effective assistance in optimizing thermal systems, particularly in dealing with complex systems and/or cases where conventional optimization techniques cannot be applied. The principles of thermoeconomics, as embodied in the specific exergy cost (SPECO) and exergy-cost-energy-mass (EXCEM) methods, are used here to determine changes in the design parameters of the cycle that improve the cost effectiveness of the overall system. It is found that the cost rate of exergy destruction varies between $1 and $15 per kilogram of hydrogen produced; and the exergoeconomic factor between 0.5 and 0.02 as the cost of hydrogen rises from $2.8 to $20 per kg of hydrogen produced. The hydrogen cost is inversely related to the exergoeconomic factor, plant capacity and energy/exergy efficiencies. Based on the cycle's design parameters and conditions the hydrogen production cost is calculated as $3.8/kg hydrogen. Also, an integrated Cu-Cl cycle hydrogen production system, based on nuclear and renewable energy sources, is investigated. Nuclear and renewable energy sources are reviewed to determine the most appropriate option to couple with the Cu-Cl cycle. An environmental impact assessment is conducted and compared to the conventional methods using fossil fuels and other options. Some cost assessment studies of hydrogen production are presented for this integrated system. The results show that hydrogen production cost could drop down to as low as 2.8 $/kg. The results are expected to assist ongoing efforts to increase the economic viability of the Cu-Cl cycle, and to reduce product costs of potential commercial versions of this process.

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 724 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 724 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Scientific and Technical Aerospace Reports

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ISBN 13 :
Total Pages : 892 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis Scientific and Technical Aerospace Reports by :

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1994 with total page 892 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Thermal Hydraulic Analyses for Coupling High Temperature Gas-Cooled Reactor to Hydrogen Plant

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)

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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.

Transactions of the American Nuclear Society

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ISBN 13 :
Total Pages : 952 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Transactions of the American Nuclear Society by : American Nuclear Society

Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 2001 with total page 952 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Structural Alloys for Nuclear Energy Applications

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Publisher : Newnes
ISBN 13 : 012397349X
Total Pages : 673 pages
Book Rating : 4.1/5 (239 download)

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Book Synopsis Structural Alloys for Nuclear Energy Applications by : Robert Odette

Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 673 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors’ unique personal insight from decades of frontline research, engineering and management. Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.