Advanced Reactors Intermediate Heat Exchanger Ihx Coupling
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Advanced Reactors Intermediate Heat Exchanger Ihx Coupling
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Author :
language : en
Publisher:
Release Date : 2016
Advanced Reactors Intermediate Heat Exchanger Ihx Coupling written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2016 with categories.
The overall goal of the research project was to model the behavior of the advanced reactorintermediate heat exchange system and to develop advanced control techniques for off-normal conditions. The specific objectives defined for the project were: 1. To develop the steady-state thermal hydraulic design of the intermediate heat exchanger (IHX); 2. To develop mathematical models to describe the advanced nuclear reactor-IHX-chemical process/power generation coupling during normal and off-normal operations, and to simulate models using multiphysics software; 3. To develop control strategies using genetic algorithm or neural network techniques and couple these techniques with the multiphysics software; 4. To validate the models experimentally The project objectives were accomplished by defining and executing four different tasks corresponding to these specific objectives. The first task involved selection of IHX candidates and developing steady state designs for those. The second task involved modeling of the transient and offnormal operation of the reactor-IHX system. The subsequent task dealt with the development of control strategies and involved algorithm development and simulation. The last task involved experimental validation of the thermal hydraulic performances of the two prototype heat exchangers designed and fabricated for the project at steady state and transient conditions to simulate the coupling of the reactor- IHX-process plant system. The experimental work utilized the two test facilities at The Ohio State University (OSU) including one existing High-Temperature Helium Test Facility (HTHF) and the newly developed high-temperature molten salt facility.
Analysis Of Transients And Control Of Advanced High Temperature Reactor Coupled Heat Exchangers System
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Author : Isaac James Skavdahl
language : en
Publisher:
Release Date : 2016
Analysis Of Transients And Control Of Advanced High Temperature Reactor Coupled Heat Exchangers System written by Isaac James Skavdahl and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2016 with Nuclear reactors categories.
Control of advanced reactor system consisting of a nuclear reactor, an intermediate heat exchanger (IHX), and a secondary heat exchanger (SHX) is investigated in this research. Initial transient analysis of the system was conducted using commercially available process simulation softwares PRO-II and DYNSIM. System parameters of significance--controlled and manipulated variables--were identified, and a control strategy was developed to maintain the controlled variables at their set points. The system response was simulated for various load disturbances, initially for the coupled heat exchangers system, followed by incorporation of the reactor dynamics in the system. Alternate strategies to control the temperature entering the process or power conversion unit (PCU) by either manipulating the secondary loop flow rate, controlling reactor power, or a combination of the two methods were investigated. Combining both methods of control showed great utility in controlling the temperature entering the process and may be an ideal method for control.
Thermal Economic Optimization And Structural Evaluation For An Advanced Intermediate Heat Exchanger Design
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Author : Xiaoqin Zhang
language : en
Publisher:
Release Date : 2016
Thermal Economic Optimization And Structural Evaluation For An Advanced Intermediate Heat Exchanger Design written by Xiaoqin Zhang and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2016 with categories.
Coupling the s-CO2 Brayton cycle to the advanced nuclear reactors generally requires an intermediate heat exchanger (IHX). From an economic viewpoint, it is important to reduce the size and cost of IHX, but at the same time, the thermal hydraulic performances should not be deteriorated. Printed-circuit heat exchanger (PCHE), one of advanced compact heat exchangers, has been demonstrated as a competitive candidate. This thesis mainly focuses on designing a PCHE-type advanced IHX with innovative surface geometry with thermal, economic and mechanical consideration. Among the four outstanding surface geometries, zigzag and S-shaped fin channels are selected for a helium-to-s-CO2 IHX. Since the thermal-hydraulic correlations of the zigzag channel with a variety of geometrical parameters are available, a thermal-economic optimization is carried out to optimize the design of zigzag channel. For such multi-objective optimization problem, the annual total cost and heat exchanger thermal effectiveness are selected as two objectives functions. NSGA-II (a fast and elitist non-dominated sorting genetic algorithm), one of the widely used multi-objective genetic algorithms, is used for searching a group of Pareto-optimal designs. It is found that among the Pareto-optimal solutions, the total cost gradually increases with the thermal effectiveness between 88 and 95% while rises rapidly after the heat exchanger effectiveness exceeds around 95%. The sensitivity study shows that for the solutions with thermal effectiveness below around 95% the heat exchanger core physical length is the dominant factor that causes conflict between the total cost and thermal effectiveness. A similar trend can be observed from both the basic and extended design space. The final selection of the optimal designs obtained from the thermal-economic optimization requires a structural evaluation of surface geometry, especially for high-temperature high-pressure applications. S-shaped fin channels are chosen for preliminary structural assessment using numerical simulation due to the geometrical complexity and expected severe stress concentration. It is found that the excessive stress concentrations occur at tips of S-shaped fins when imposed with high-pressure differential loading. A small portion of the fin yields while the rest of the fin body remains low-stress level. The design and service limit prescribed in the ASME BPVC code is used to evaluate local stresses of the S-shaped fin, and according to the criterion, the reference model was allowed for 11.5 years of service with small portion of fin body yielded.
Strategic Need For A Multi Purpose Thermal Hydraulic Loop For Support Of Advanced Reactor Technologies
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Author :
language : en
Publisher:
Release Date : 2014
Strategic Need For A Multi Purpose Thermal Hydraulic Loop For Support Of Advanced Reactor Technologies written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2014 with categories.
This report presents a conceptual design for a new high-temperature multi fluid, multi loop test facility for the INL to support thermal hydraulic, materials, and thermal energy storage research for nuclear and nuclear-hybrid applications. In its initial configuration, the facility will include a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed with this facility include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs) at prototypical operating conditions, flow and heat transfer issues related to core thermal hydraulics in advanced helium-cooled and salt-cooled reactors, and evaluation of corrosion behavior of new cladding materials and accident-tolerant fuels for LWRs at prototypical conditions. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST) facility. Research performed in this facility will advance the state of the art and technology readiness level of high temperature intermediate heat exchangers (IHXs) for nuclear applications while establishing the INL as a center of excellence for the development and certification of this technology. The thermal energy storage capability will support research and demonstration activities related to process heat delivery for a variety of hybrid energy systems and grid stabilization strategies. Experimental results obtained from this research will assist in development of reliable predictive models for thermal hydraulic design and safety codes over the range of expected advanced reactor operating conditions. Proposed/existing IHX heat transfer and friction correlations and criteria will be assessed with information on materials compatibility and instrumentation needs. The experimental database will guide development of appropriate predictive methods and be available for code verification and validation (V & V) related to these systems.
Review Of Current Experience On Intermediate Heat Exchanger Ihx And A Recommended Code Approach
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Author :
language : en
Publisher:
Release Date : 2010
Review Of Current Experience On Intermediate Heat Exchanger Ihx And A Recommended Code Approach written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2010 with categories.
The purpose of the ASME/DOE Gen IV Task 7 Part I is to review the current experience on various high temperature reactor intermediate heat exchanger (IHX) concepts. There are several different IHX concepts that could be envisioned for HTR/VHTR applications in a range of temperature from 850C to 950C. The concepts that will be primarily discussed herein are: (1) Tubular Helical Coil Heat Exchanger (THCHE); (2) Plate-Stamped Heat Exchanger (PSHE); (3) Plate-Fin Heat Exchanger (PFHE); and (4) Plate-Machined Heat Exchanger (PMHE). The primary coolant of the NGNP is potentially subject to radioactive contamination by the core as well as contamination from the secondary loop fluid. To isolate the radioactivity to minimize radiation doses to personnel, and protect the primary circuit from contamination, intermediate heat exchangers (IHXs) have been proposed as a means for separating the primary circuit of the NGNP (Next Generation Nuclear Plant) or other process heat application from the remainder of the plant. This task will first review the different concepts of IHX that could be envisioned for HTR/VHTR applications in a range of temperature from 850 to 950 C. This will cover shell-and-tube and compact designs (including the platefin concept). The review will then discuss the maturity of the concepts in terms of design, fabricability and component testing (or feedback from experience when applicable). Particular attention will be paid to the feasibility of developing the IHX concepts for the NGNP with operation expected in 2018-2021. This report will also discuss material candidates for IHX applications and will discuss specific issues that will have to be addressed in the context of the HTR design (thermal aging, corrosion, creep, creep-fatigue, etc). Particular attention will be paid to specific issues associated with operation at the upper end of the creep regime.
Advanced Reactor Concepts Arc
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Author : Ali Zamani Paydar
language : en
Publisher: Elsevier
Release Date : 2023-07-20
Advanced Reactor Concepts Arc written by Ali Zamani Paydar and has been published by Elsevier this book supported file pdf, txt, epub, kindle and other format this book has been release on 2023-07-20 with Technology & Engineering categories.
Nuclear engineers advancing the energy transition are understanding more about the next generation of nuclear plants; however, it is still difficult to access all the critical types, concepts, and applications in one location. Advanced Reactor Concepts (ARC): A New Nuclear Power Plant Perspective Producing Energy gives engineers and nuclear engineering researchers the comprehensive tools to get up to date on the latest technology supporting generation IV nuclear plant systems. After providing a brief history of this area, alternative technology is discussed such as electromagnetic pumps, heat pipes as control devices, Nuclear Air-Brayton Combined Cycles integration, and instrumentation helping nuclear plants to provide dispatchable electricity to the grid and heat to industry. Packed with examples of all the types, benefits, and challenges involved, Advanced Reactor Concepts (ARC) delivers the go-to reference that engineers need to advance safe nuclear energy as a low-carbon option. Describes theory and concepts on generation IV technology such as advanced reactor concepts (ARC) and electromagnetic pumps, and compares different types and sizes. Sets out the energy transition with critical carbon-free technology that can supplement intermittent power sources such as wind and solar. Explains alternative heat storage technology, including Nuclear Air-Brayton Combined Cycles. Introduces advanced main instrumentation systems for in-core probes.
Compact Heat Exchangers
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Author : J.E. Hesselgreaves
language : en
Publisher: Elsevier
Release Date : 2001-05-08
Compact Heat Exchangers written by J.E. Hesselgreaves and has been published by Elsevier this book supported file pdf, txt, epub, kindle and other format this book has been release on 2001-05-08 with Technology & Engineering categories.
This book presents the ideas and industrial concepts in compact heat exchanger technology that have been developed in the last 10 years or so. Historically, the development and application of compact heat exchangers and their surfaces has taken place in a piecemeal fashion in a number of rather unrelated areas, principally those of the automotive and prime mover, aerospace, cryogenic and refrigeration sectors. Much detailed technology, familiar in one sector, progressed only slowly over the boundary into another sector. This compartmentalisation was a feature both of the user industries themselves, and also of the supplier, or manufacturing industries. These barriers are now breaking down, with valuable cross-fertilisation taking place. One of the industrial sectors that is waking up to the challenges of compact heat exchangers is that broadly defined as the process sector. If there is a bias in the book, it is towards this sector. Here, in many cases, the technical challenges are severe, since high pressures and temperatures are often involved, and working fluids can be corrosive, reactive or toxic. The opportunities, however, are correspondingly high, since compacts can offer a combination of lower capital or installed cost, lower temperature differences (and hence running costs), and lower inventory. In some cases they give the opportunity for a radical re-think of the process design, by the introduction of process intensification (PI) concepts such as combining process elements in one unit. An example of this is reaction and heat exchange, which offers, among other advantages, significantly lower by-product production.To stimulate future research, the author includes coverage of hitherto neglected approaches, such as that of the Second Law (of Thermodynamics), pioneered by Bejan and co- workers. The justification for this is that there is increasing interest in life-cycle and sustainable approaches to industrial activity as a whole, often involving exergy (Second Law) analysis. Heat exchangers, being fundamental components of energy and process systems, are both savers and spenders of exergy, according to interpretation.
Asme Code Considerations For The Compact Heat Exchanger
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Author :
language : en
Publisher:
Release Date : 2015
Asme Code Considerations For The Compact Heat Exchanger written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2015 with categories.
The mission of the U.S. Department of Energy (DOE), Office of Nuclear Energy is to advance nuclear power in order to meet the nation's energy, environmental, and energy security needs. Advanced high temperature reactor systems such as sodium fast reactors and high and very high temperature gas-cooled reactors are being considered for the next generation of nuclear reactor plant designs. The coolants for these high temperature reactor systems include liquid sodium and helium gas. Supercritical carbon dioxide (sCO2), a fluid at a temperature and pressure above the supercritical point of CO2, is currently being investigated by DOE as a working fluid for a nuclear or fossil-heated recompression closed Brayton cycle energy conversion system that operates at 550°C (1022°F) at 200 bar (2900 psi). Higher operating temperatures are envisioned in future developments. All of these design concepts require a highly effective heat exchanger that transfers heat from the nuclear or chemical reactor to the chemical process fluid or the to the power cycle. In the nuclear designs described above, heat is transferred from the primary to the secondary loop via an intermediate heat exchanger (IHX) and then from the intermediate loop to either a working process or a power cycle via a secondary heat exchanger (SHX). The IHX is a component in the primary coolant loop which will be classified as "safety related." The intermediate loop will likely be classified as "not safety related but important to safety." These safety classifications have a direct bearing on heat exchanger design approaches for the IHX and SHX. The very high temperatures being considered for the VHTR will require the use of very high temperature alloys for the IHX and SHX. Material cost considerations alone will dictate that the IHX and SHX be highly effective; that is, provide high heat transfer area in a small volume. This feature must be accompanied by low pressure drop and mechanical reliability and robustness. Classic shell and tube designs will be large and costly, and may only be appropriate in steam generator service in the SHX where boiling inside the tubes occurs. For other energy conversion systems, all of these features can be met in a compact heat exchanger design. This report will examine some of the ASME Code issues that will need to be addressed to allow use of a Code-qualified compact heat exchanger in IHX or SHX nuclear service. Most effort will focus on the IHX, since the safety-related (Class A) design rules are more extensive than those for important-to-safety (Class B) or commercial rules that are relevant to the SHX.
Energy Research Advisory Board Civilian Nuclear Power Panel Subpanel Ii
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Author :
language : en
Publisher:
Release Date : 1986
Energy Research Advisory Board Civilian Nuclear Power Panel Subpanel Ii written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1986 with Nuclear reactors categories.
Secondary Heat Exchanger Design And Comparison For Advanced High Temperature Reactor
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Author :
language : en
Publisher:
Release Date : 2012
Secondary Heat Exchanger Design And Comparison For Advanced High Temperature Reactor written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with categories.
The goals of next generation nuclear reactors, such as the high temperature gas-cooled reactor and advance high temperature reactor (AHTR), are to increase energy efficiency in the production of electricity and provide high temperature heat for industrial processes. The efficient transfer of energy for industrial applications depends on the ability to incorporate effective heat exchangers between the nuclear heat transport system and the industrial process heat transport system. The need for efficiency, compactness, and safety challenge the boundaries of existing heat exchanger technology, giving rise to the following study. Various studies have been performed in attempts to update the secondary heat exchanger that is downstream of the primary heat exchanger, mostly because its performance is strongly tied to the ability to employ more efficient conversion cycles, such as the Rankine super critical and subcritical cycles. This study considers two different types of heat exchangers--helical coiled heat exchanger and printed circuit heat exchanger--as possible options for the AHTR secondary heat exchangers with the following three different options: (1) A single heat exchanger transfers all the heat (3,400 MW(t)) from the intermediate heat transfer loop to the power conversion system or process plants; (2) Two heat exchangers share heat to transfer total heat of 3,400 MW(t) from the intermediate heat transfer loop to the power conversion system or process plants, each exchanger transfers 1,700 MW(t) with a parallel configuration; and (3) Three heat exchangers share heat to transfer total heat of 3,400 MW(t) from the intermediate heat transfer loop to the power conversion system or process plants. Each heat exchanger transfers 1,130 MW(t) with a parallel configuration. A preliminary cost comparison will be provided for all different cases along with challenges and recommendations.