Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Design Of Passive Decay Heat Removal System For The Lead Cooled Flexible Conversion Ratio Fast Reactor
Download Design Of Passive Decay Heat Removal System For The Lead Cooled Flexible Conversion Ratio Fast Reactor full books in PDF, epub, and Kindle. Read online Design Of Passive Decay Heat Removal System For The Lead Cooled Flexible Conversion Ratio Fast Reactor ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Design of Passive Decay Heat Removal System for the Lead Cooled Flexible Conversion Ratio Fast Reactor by : Joshua J. Whitman
Download or read book Design of Passive Decay Heat Removal System for the Lead Cooled Flexible Conversion Ratio Fast Reactor written by Joshua J. Whitman and published by . This book was released on 2007 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt: The lead-cooled flexible conversion ratio fast reactor shows many benefits over other fast-reactor designs; however, the higher power rating and denser primary coolant present difficulties for the design of a passive decay heat removal system. In order to achieve passive cooling, enhancements are needed over current designs, such as the S-PRISM and ABR, which utilize passive cooling through the reactor vessel to atmospheric air. Enhancements such as axial fins, a perforated plate, and round indentations, or dimples, were considered as additions to the hot air riser to increase heat transfer. Other enhancements include a liquid metal bond between the reactor and guard vessels, and a dual-level design which introduces ambient temperature air halfway up the vessel wall. A code was written in Java to simulate these conditions, leading to a promising case using dimples on the guard vessel wall as the primary mode of heat transfer enhancement, and including the dual-level design. A conservative estimate of dimple performance indicates that during a passive decay heat removal shutdown, bulk primary coolant temperature will peak at 713 'C, giving a 12 OC margin to clad failure. Attempts were made to refine the uncertainty within the calculations using a computational fluid dynamics code, Fluent, but these ultimately were unsuccessful. Additional studies were conducted on the static stress imparted on the vessel, and the dynamic stress caused by a seismic event. The static stress was found to be within ASME code limits. Seismic analysis determined that a seismic isolation scheme would be necessary in order to prevent damage to the vessel during an earthquake.
Book Synopsis Flexible Conversion Ratio Fast Reactor Systems Evaluation by :
Download or read book Flexible Conversion Ratio Fast Reactor Systems Evaluation written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Conceptual designs of lead-cooled and liquid salt-cooled fast flexible conversion ratio reactors were developed. Both concepts have cores reated at 2400 MWt placed in a large-pool-type vessel with dual-free level, which also contains four intermediate heat exchanges coupling a primary coolant to a compact and efficient supercritical CO2 Brayton cycle power conversion system. Decay heat is removed passively using an enhanced Reactor Vessel Auxiliary Cooling System and a Passive Secondary Auxiliary Cooling System. The most important findings were that (1) it is feasible to design the lead-cooled and salt-cooled reactor with the flexible conversion ratio (CR) in the range of CR=0 and CR=1 n a manner that achieves inherent reactor shutdown in unprotected accidents, (2) the salt-cooled reactor requires Lithium thermal Expansion Modules to overcme the inherent salt coolant's large positive coolant temperature reactivity coefficient, (3) the preferable salt for fast spectrum high power density cores is NaCl-Kcl-MgCl2 as opposed to fluoride salts due to its better themal-hydraulic and neutronic characteristics, and (4) both reactor, but attain power density 3 times smaller than that of the sodium-cooled reactor.
Book Synopsis Issues in Water and Power Engineering: 2011 Edition by :
Download or read book Issues in Water and Power Engineering: 2011 Edition written by and published by ScholarlyEditions. This book was released on 2012-01-09 with total page 651 pages. Available in PDF, EPUB and Kindle. Book excerpt: Issues in Water and Power Engineering / 2011 Edition is a ScholarlyEditions™ eBook that delivers timely, authoritative, and comprehensive information about Water and Power Engineering. The editors have built Issues in Water and Power Engineering: 2011 Edition on the vast information databases of ScholarlyNews.™ You can expect the information about Water and Power Engineering in this eBook to be deeper than what you can access anywhere else, as well as consistently reliable, authoritative, informed, and relevant. The content of Issues in Water and Power Engineering: 2011 Edition has been produced by the world’s leading scientists, engineers, analysts, research institutions, and companies. All of the content is from peer-reviewed sources, and all of it is written, assembled, and edited by the editors at ScholarlyEditions™ and available exclusively from us. You now have a source you can cite with authority, confidence, and credibility. More information is available at http://www.ScholarlyEditions.com/.
Book Synopsis Design of a 2400MW Liquid-salt Cooled Flexible Conversion Ratio Reactor by : Robert C. Petroski
Download or read book Design of a 2400MW Liquid-salt Cooled Flexible Conversion Ratio Reactor written by Robert C. Petroski and published by . This book was released on 2008 with total page 145 pages. Available in PDF, EPUB and Kindle. Book excerpt: A 2400MWth liquid-salt cooled flexible conversion ratio reactor was designed, utilizing the ternary chloride salt NaCl-KCl-MgCI2 (30%-20%-50%) as coolant. The reference design uses a wire-wrapped, hex lattice core, and is able to achieve a core power density of 130 kW/1 with a core pressure drop of 700kPa and a maximum cladding temperature under 650'C. Four kidney- shaped conventional tube-in-shell heat exchangers are used to connect the primary system to a 5450C supercritical CO2 power conversion system. The core, intermediate heat exchangers, and reactor coolant pumps fit in a vessel approximately 10 meters in diameter and less than 20 meters high. Lithium expansion modules (LEMs) were used to reconcile conflicting thermal hydraulic and reactor physics requirements in the liquid salt core. Use of LEMs allowed the design of a very favorable reactivity response which greatly benefits transient mitigation. A reactor vessel auxiliary cooling system (RVACS) and four redundant passive secondary auxiliary cooling systems (PSACS) are used to provide passive heat removal, and are able to successfully mitigate both an unprotected station blackout transient as well as protected transients in which a scram occurs. Additionally, it was determined that the power conversion system can be used to mitigate both a loss of flow accident and an unprotected transient overpower.
Book Synopsis Advanced Power Generation Systems by : Yatish T. Shah
Download or read book Advanced Power Generation Systems written by Yatish T. Shah and published by CRC Press. This book was released on 2022-12-21 with total page 523 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advanced Power Generation Systems: Thermal Sources evaluates advances made in heat-to-power technologies for conventional combustion heat and nuclear heat, along with natural sources of geothermal, solar, and waste heat generated from the use of different sources. These advances will render the landscape of power generation significantly different in just a few decades. This book covers the commercial viability of advanced technologies and identifies where more work needs to be done. Since power is the future of energy, these technologies will remain sustainable over a long period of time. Key Features Covers power generation and heat engines Details photovoltaics, thermo-photovoltaics, and thermoelectricity Includes discussion of nuclear and renewable energy as well as waste heat This book will be useful for advanced students, researchers, and professionals interested in power generation and energy industries.
Book Synopsis Risk-informed Design Changes for a Passive Cooling System by : Giovanbattista Patalano
Download or read book Risk-informed Design Changes for a Passive Cooling System written by Giovanbattista Patalano and published by . This book was released on 2007 with total page 121 pages. Available in PDF, EPUB and Kindle. Book excerpt: The failure probability of a passive decay heat removal system after a LOCA is evaluated as part of a risk-informed design process for a helium-cooled fast reactor. The system was modeled using RELAP5-3D. The epistemic uncertainties in input parameters as well as the epistemic model uncertainties in the code were assessed and propagated through the model using Latin hypercube sampling. The changes in the design that we investigated reduced the overall failure probability of the system by reducing the impact of the major contributor to the failure probability. Sensitivity analyses led to two unexpected results. First, the key factors affecting the system failure probability are the location of the thermal insulation (inside or outside the hot leg) and the uncertainty in the insulation thermal conductivity. Second, the heat transfer coefficient in the core is not as important as one might expect. Our results show that the heat transfer coefficient in the containment structures is more important. Different methods for sensitivity analysis were applied and gave consistent results.
Book Synopsis Passive Decay Heat Removal System for Water-cooled Nuclear Reactors by :
Download or read book Passive Decay Heat Removal System for Water-cooled Nuclear Reactors written by and published by . This book was released on 1990 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document describes passive decay-heat removal system for a water-cooled nuclear reactor which employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated evaporator located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it will become exposed to steam. Vapor produced in the evaporator passes upward to the condenser above the normal water level. In operation, condensation in the condenser removes heat from the system, and the condensed liquid is returned to the evaporator. The system is disposed such that during normal reactor operations where the water level is at its usual position, very little heat will be removed from the system, but during emergency, low water level conditions, substantial amounts of decay heat will be removed.
Book Synopsis Reliability Analysis of a Passive Cooling System Using a Response Surface with an Application to the Flexible Conversion Ratio Reactor by : Christopher Joseph Fong
Download or read book Reliability Analysis of a Passive Cooling System Using a Response Surface with an Application to the Flexible Conversion Ratio Reactor written by Christopher Joseph Fong and published by . This book was released on 2008 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt: A comprehensive risk-informed methodology for passive safety system design and performance assessment is presented and demonstrated on the Flexible Conversion Ratio Reactor (FCRR). First, the methodology provides a framework for risk-informed design decisions and as an example two design options for a decay heat removal system are assessed and quantitatively compared. Next, the reliability of the system is assessed by quantifying the uncertainties related to system performance and propagating these uncertainties through a response surface using Monte Carlo simulation. Finally, a sensitivity study is performed to measure the relative effects of each parameter and to identify ways to maintain, improve, and monitor system performance.
Book Synopsis Energy Conversion by : D. Yogi Goswami
Download or read book Energy Conversion written by D. Yogi Goswami and published by CRC Press. This book was released on 2017-07-06 with total page 1193 pages. Available in PDF, EPUB and Kindle. Book excerpt: This handbook surveys the range of methods and fuel types used in generating energy for industry, transportation, and heating and cooling of buildings. Solar, wind, biomass, nuclear, geothermal, ocean and fossil fuels are discussed and compared, and the thermodynamics of energy conversion is explained. Appendices are provided with fully updated data. Thoroughly revised, this second edition surveys the latest advances in energy conversion from a wide variety of currently available energy sources. It describes energy sources such as fossil fuels, biomass (including refuse-derived biomass fuels), nuclear, solar radiation, wind, geothermal, and ocean, then provides the terminology and units used for each energy resource and their equivalence. It includes an overview of the steam power cycles, gas turbines, internal combustion engines, hydraulic turbines, Stirling engines, advanced fossil fuel power systems, and combined-cycle power plants. It outlines the development, current use, and future of nuclear power.
Book Synopsis Liquid Metal Cooled Reactors by : International Atomic Energy Agency
Download or read book Liquid Metal Cooled Reactors written by International Atomic Energy Agency and published by . This book was released on 2007 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.
Book Synopsis Experimental and Analytical Studies of Passive Shutdown Heat Removal Systems by :
Download or read book Experimental and Analytical Studies of Passive Shutdown Heat Removal Systems written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Using a naturally circulating air stream to remove shutdown decay heat from a nuclear reactor vessel is a key feature of advanced liquid metal reactor (LMR) concepts developed by potential vendors selected by the Department of Energy. General Electric and Rockwell International continue to develop innovative design concepts aimed at improving safety, lowering plant costs, simplifying plant operation, reducing construction times, and most of all, enhancing plant licensability. The reactor program at Argonne National Laboratory (ANL) provides technical support to both organizations. The method of shutdown heat removal proposed employs a totally passive cooling system that rejects heat from the reactor by radiation and natural convection to air. The system is inherently reliable since it is not subject failure modes associated with active decay cooling systems. The system is designed to assure adequate cooling of the reactor under abnormal operating conditions associated with loss of heat removal through other heat transport paths.
Book Synopsis Conceptual Design of a Water Cooled Reactor with Passive Decay Heat Removal. Final Performance Technical Report, September 30, 1992--October 31, 1995 by :
Download or read book Conceptual Design of a Water Cooled Reactor with Passive Decay Heat Removal. Final Performance Technical Report, September 30, 1992--October 31, 1995 written by and published by . This book was released on 1996 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: A conceptual design was performed of a light water moderated reactor with power output in the range of 1000 MWe, which allows passive decay heat removal (i.e., the heat path to the ultimate heat sink, ambient air, is provided by natural heat transfer mechanisms such as conduction, radiation and free convection). This eliminates the reliance on the availability of emergency pumped cooling. The design ensures that the fuel remains within safety limits even in the total absence of coolant in the primary system. The challenge met was the achievement of this passive cooling capability while simultaneously achieving a high, 1000 MWe power rating.
Book Synopsis Design and Analysis of a Passive Heat Removal System for a Small Modular Reactor Using STAR CCM+ by : Raymond Michael Fanning
Download or read book Design and Analysis of a Passive Heat Removal System for a Small Modular Reactor Using STAR CCM+ written by Raymond Michael Fanning and published by . This book was released on 2017 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Next generation nuclear power plants, specifically small modular reactor designs, are the best alternative to fossil fuels for power generation due to their power density and low carbon emissions and constant awareness of safety concerns. A promising safety feature of new designs is the removal of heat by passive systems in accident scenarios. The passive systems require no moving parts and no intervention by personnel. These systems must be accurately simulated for better understanding of the heat transport phenomena: natural convection cooling. Due to the fact that most work developing these passive heat removal systems are proprietary information, a passive heat removal system for a small modular reactor was designed and simulated in Star CCM+ to evaluate the capability of natural convective flows to remove decay heat in a shutdown scenario. The size and dimensions of the heat exchanger are based on the Westinghouse-SMR design. The design of the passive heat removal system was a hexagonal lattice heat exchanger. The final design was projected to dissipate the 56MW of decay heat at the rate simulated in Star CCM+"--Abstract, page iv.
Book Synopsis Experimental Validation of Passive Safety System Models by : Nicolas Zweibaum
Download or read book Experimental Validation of Passive Safety System Models written by Nicolas Zweibaum and published by . This book was released on 2015 with total page 231 pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of advanced nuclear reactor technology requires understanding of complex, integrated systems that exhibit novel phenomenology under normal and accident conditions. The advent of passive safety systems and enhanced modular construction methods requires the development and use of new frameworks to predict the behavior of advanced nuclear reactors, both from a safety standpoint and from an environmental impact perspective. This dissertation introduces such frameworks for scaling of integral effects tests for natural circulation in fluoride-salt-cooled, high-temperature reactors (FHRs) to validate evaluation models (EMs) for system behavior; subsequent reliability assessment of passive, natural- circulation-driven decay heat removal systems, using these validated models; evaluation of life cycle carbon dioxide emissions as a key environmental impact metric; and recommendations for further work to apply these frameworks in the development and optimization of advanced nuclear reactor designs. In this study, the developed frameworks are applied to the analysis of the Mark 1 pebble-bed FHR (Mk1 PB-FHR) under current investigation at the University of California, Berkeley (UCB). The capability to validate integral transient response models is a key issue for licensing new reactor designs. This dissertation presents the scaling strategy, design and fabrication aspects, and startup testing results from the Compact Integral Effects Test (CIET) facility at UCB, which reproduces the thermal hydraulic response of an FHR under forced and natural circulation operation. CIET provides validation data to confirm the performance of the direct reactor auxiliary cooling system (DRACS) in an FHR, used for natural-circulation-driven decay heat removal, under a set of reference licensing basis events, as predicted by best-estimate codes such as RELAP5-3D. CIET uses a simulant fluid, Dowtherm A oil, which at relatively low temperatures (50-120°C) matches the Prandtl, Reynolds, Froude and Grashof numbers of the major liquid salts simultaneously, at approximately 50% geometric scale and heater power under 2% of prototypical conditions. The studies reported here include isothermal pressure drop tests performed during startup testing of CIET, with extensive pressure data collection to determine friction losses in the system, as well as subsequent heated tests, from parasitic heat loss tests to more complex feedback control tests and natural circulation experiments. For initial code validation, coupled steady-state single-phase natural circulation loops and simple forced cooling transients were conducted in CIET. For various heat input levels and temperature boundary conditions, fluid mass flow rates and temperatures were compared between RELAP5- 3D results, analytical solutions when available, and experimental data. This study shows that RELAP5-3D provides excellent predictions of steady-state natural circulation and simple transient forced cooling in CIET. The code predicts natural circulation mass flow rates within 8%, and steady-state and transient fluid temperatures, under both natural and forced circulation, within 2°C of experimental data, suggesting that RELAP5-3D is a good EM to use to design and license FHRs. A key element in design and licensing of new reactor technology lies in the analysis of the plant response to a variety of potential transients. When applicable, this involves understanding of passive safety system behavior. This dissertation develops a framework to assess reliability and propose design optimization and risk mitigation strategies associated with passive decay heat removal systems, applied to the Mk1 PB-FHR DRACS. This investigation builds upon previous detailed design work for Mk1 components and the use of RELAP5-3D models validated for FHR natural circulation phenomenology. For risk assessment, reliability of the point design of the passive safety system for the Mk1 PB-FHR, which depends on the ability of various structures to fulfill their safety functions, is studied. Whereas traditional probabilistic risk assessment (PRA) methods are based on event and fault trees for components of the system that perform in a binary way - operating or not operating -, this study is mostly based on probability distributions of heat load compared to the capacity of the system to remove heat, as recommended by the reliability methods for passive safety functions (RMPS) that are used here. To reduce computational time, the use of response surfaces to describe the system in a simplified manner, in the context of RMPS, is also demonstrated. The design optimization and risk mitigation part proposes a framework to study the elements of the design of the reactor, and more specifically its passive safety cooling system, which can contribute to enhanced reliability of heat removal under accident conditions. Risk mitigation measures based on design, startup testing, in-service inspection and online monitoring are proposed to narrow probability distributions of key parameters of the system and increase reliability and safety. Another major aspect in the development of novel energy systems is the assessment of their impacts on the environment compared to current technologies. While most existing life cycle assessment (LCA) studies have been applied to conventional nuclear power plants, this dissertation proposes a framework to extend such studies to advanced reactor designs, using the example of the Mk1 PB-FHR. The Mk1 uses a nuclear air-Brayton combined cycle designed to produce 100 MWe of base-load electricity when operated with only nuclear heat, and 242 MWe using natural gas co-firing for peaking power. The Mk1 design provides a basis for quantities and costs of major classes of materials involved in building the reactor and fabricating fuel, and operation parameters. Existing data and economic input-output LCA models are used to calculate greenhouse gas emissions per kWh of electricity produced over the life cycle of the reactor. Baseline life cycle emissions from the Mk1 PB-FHR in base-load configuration are 26% lower than average Generation II light water reactors in the U.S., 98% lower than average U.S. coal plants and 96% lower than average U.S. natural gas combined cycle plants using the same turbine technology. In peaking configuration, due to its nuclear component and higher thermal efficiency, the Mk1 plant only produces 32% of the emissions of average U.S. gas turbine simple cycle peaking plants. One key contribution to life cycle emissions results from the amount and type of concrete used for reactor construction. This is an incentive to develop innovative construction methods using optimized steel-concrete composite wall modules and new concrete mixes to reduce life cycle emissions from the Mk1 and other advanced reactor designs.
Book Synopsis Design of Complex Systems to Achieve Passive Safety by : Raluca Olga Scarlat
Download or read book Design of Complex Systems to Achieve Passive Safety written by Raluca Olga Scarlat and published by . This book was released on 2012 with total page 352 pages. Available in PDF, EPUB and Kindle. Book excerpt: This dissertation treats system design, modeling of transient system response, and characterization of individual phenomena and demonstrates a framework for integration of these three activities early in the design process of a complex engineered system. A system analysis framework for prioritization of experiments, modeling, and development of detailed design is proposed. Two fundamental topics in thermal-hydraulics are discussed, which illustrate the integration of modeling and experimentation with nuclear reactor design and safety analysis: thermal-hydraulic modeling of heat generating pebble bed cores, and scaled experiments for natural circulation heat removal with Boussinesq liquids. The case studies used in this dissertation are derived from the design and safety analysis of a pebble bed fluoride salt cooled high temperature nuclear reactor (PB-FHR), currently under development in the United States at the university and national laboratories level. In the context of the phenomena identification and ranking table (PIRT) methodology, new tools and approaches are proposed and demonstrated here, which are specifically relevant to technology in the early stages of development, and to analysis of passive safety features. A system decomposition approach is proposed. Definition of system functional requirements complements identification and compilation of the current knowledge base for the behavior of the system. Two new graphical tools are developed for ranking of phenomena importance: a phenomena ranking map, and a phenomena identification and ranking matrix (PIRM). The functional requirements established through this methodology were used for the design and optimization of the reactor core, and for the transient analysis and design of the passive natural circulation driven decay heat removal system for the PB-FHR. A numerical modeling approach for heat-generating porous media, with multi-dimensional fluid flow is presented. The application of this modeling approach to the PB-FHR annular pebble bed core cooled by fluoride salt mixtures generated a model that is called Pod. Pod was used to show the resilience of the PB-FHR core to generation of hot spots or cold spots, due to the effect of buoyancy on the flow and temperature distribution in the packed bed. Pod was used to investigate the PB-FHR response to ATWS transients. Based on the functional requirements for the core, Pod was used to generate an optimized design of the flow distribution in the core. An analysis of natural circulation loops cooled by single-phase Boussinesq fluids is presented here, in the context of reactor design that relies on natural circulation decay heat removal, and design of scaled experiments. The scaling arguments are established for a transient natural circulation loop, for loops that have long fluid residence time, and negligible contribution of fluid inertia to the momentum equation. The design of integral effects tests for the loss of forced circulation (LOFC) for PB-FHR is discussed. The special case of natural circulation decay heat removal from a pebble bed reactor was analyzed. A way to define the Reynolds number in a multi-dimensional pebble bed was identified. The scaling methodology for replicating pebble bed friction losses using an electrically resistance heated annular pipe and a needle valve was developed. The thermophysical properties of liquid fluoride salts lead to design of systems with low flow velocities, and hence long fluid residence times. A comparison among liquid coolants for the performance of steady state natural circulation heat removal from a pebble bed was performed. Transient natural circulation experimental data with simulant fluids for fluoride salts is given here. The low flow velocity and the relatively high viscosity of the fluoride salts lead to low Reynolds number flows, and a low Reynolds number in conjunction with a sufficiently high coefficient of thermal expansion makes the system susceptible to local buoyancy effects Experiments indicate that slow exchange of stagnant fluid in static legs can play a significant role in the transient response of natural circulation loops. The effect of non-linear temperature profiles on the hot or cold legs or other segments of the flow loop, which may develop during transient scenarios, should be considered when modeling the performance of natural circulation loops. The data provided here can be used for validation of the application of thermal-hydraulic systems codes to the modeling of heat removal by natural circulation with liquid fluoride salts and its simulant fluids.
Book Synopsis Scaling Analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors During a Depressurized Loss of Forced Convection Event by : Grant C. Blake
Download or read book Scaling Analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors During a Depressurized Loss of Forced Convection Event written by Grant C. Blake and published by . This book was released on 2016 with total page 310 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system capable of removing decay heat directly from the reactor core. Its modularity makes it scalable for use in reactors with various power levels. Work has previously been completed to support inclusion of the DRACS in liquid metal reactors and fluoride-salt cooled reactors. This work supports the inclusion of DRACS in gas-cooled reactors, similarly. A scaling analysis has been completed for a DRACS module. The target prototype for this scaling analysis is a DRACS for gas-cooled fast reactor (GFR), such as in the Energy Multiplier Module (EM2). The target model for the scaling analysis is a conceptual design for the inclusion in the High Temperature Test Facility (HTTF) at Oregon State University (OSU). Also included herein is the conceptual design requirements for said scaled-down DRACS module including an instrumentation plan and SolidWorks models. Python was used with Engineering Equation Solver to determine the operating characteristics. These physical dimensions and operating characteristics were used to build models in RELAP5-3D of the scaled-down and full-scale DRACS with the intent to inform the scaling analysis results. Results from the RELAP5-3D models support the scaling analysis performed. The error was analyzed between the resulting scaling for each value from RELAP5-3D and the theoretical scaling value as found in the scaling analysis. The errors found for most of the quantities were minimal, and well within reason for simulations in RELAP5-3D. There was a significant error found in the intermediate loop velocity scaling from the RELAP5-3D model results, and this error led to other errors which are dependent on the intermediate loop velocity. The scaling of the heat transfer rates in the intermediate loop also experienced an error from the theoretical results, leading to an error in the intermediate loop DRACS heat exchanger (DHX) and natural draft heat exchanger (NDHX) numbers. The velocity error is thought to be the result of an improperly scaled intermediate loop resistance number, which cannot be investigated directly from RELAP5-3D outputs. The heat transfer error is likely due to different Nusselt number correlations in the intermediate loop from those used in the direct and natural draft loops. These correlations are selected automatically by the code, and measures could be taken in a future design to correct for this.
Book Synopsis Optimized Core Design of a Supercritical Carbon Dioxide-cooled Fast Reactor by : Christopher Stanley Handwerk
Download or read book Optimized Core Design of a Supercritical Carbon Dioxide-cooled Fast Reactor written by Christopher Stanley Handwerk and published by . This book was released on 2007 with total page 367 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) Alternative cores using traditional pin-type fuel and innovative Internally-Cooled Annular Fuel (ICAF) have also been evaluated. While the performance of the TID core is superior, the results of the pin-type core show promise, pending design modification and relaxation of the imposed core pressure drop constraint, which would come at the expense of cycle efficiency and increased decay heat removal power requirements. Nevertheless, no improvement would be able to achieve a sustainable core (i.e. conversion ratio=l) using oxide fuel without the use of external blankets for pin fuel, even without the use of diluent in the fuel. A comprehensive comparison of the thermal hydraulic and neutronic performance of TID fuel with that of the traditional pin-type fuel, as well as with the ICAF is also made, showing the fundamental reasons for their difference in performance.
