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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 225
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Book Description
This NEUP funded project, NEUP 12-3630, is for experimental, numerical and analytical studies on high-pressure steam condensation phenomena in a steel containment vessel connected to a water cooling tank, carried out at Oregon State University (OrSU) and the University of Wisconsin at Madison (UW-Madison). In the three years of investigation duration, following the original proposal, the planned tasks have been completed: (1) Performed a scaling study for the full pressure test facility applicable to the reference design for the condensation heat transfer process during design basis accidents (DBAs), modified the existing test facility to route the steady-state secondary steam flow into the high pressure containment for controllable condensation tests, and extended the operations at negative gage pressure conditions (OrSU). (2) Conducted a series of DBA and quasi-steady experiments using the full pressure test facility to provide a reliable high pressure condensation database (OrSU). (3) Analyzed experimental data and evaluated condensation model for the experimental conditions, and predicted the prototypic containment performance under accidental conditions (UW-Madison). A film flow model was developed for the scaling analysis, and the results suggest that the 1/3 scaled test facility covers large portion of laminar film flow, leading to a lower average heat transfer coefficient comparing to the prototypic value. Although it is conservative in reactor safety analysis, the significant reduction of heat transfer coefficient (50%) could under estimate the prototypic condensation heat transfer rate, resulting in inaccurate prediction of the decay heat removal capability. Further investigation is thus needed to quantify the scaling distortion for safety analysis code validation. Experimental investigations were performed in the existing MASLWR test facility at OrST with minor modifications. A total of 13 containment condensation tests were conducted for pressure ranging from 4 to 21 bar with three different static inventories of non-condensable gas. Condensation and heat transfer rates were evaluated employing several methods, notably from measured temperature gradients in the HTP as well as measured condensate formation rates. A detailed mass and energy accounting was used to assess the various measurement methods and to support simplifying assumptions required for the analysis. Condensation heat fluxes and heat transfer coefficients are calculated and presented as a function of pressure to satisfy the objectives of this investigation. The major conclusions for those tests are summarized below: (1) In the steam blow-down tests, the initial condensation heat transfer process involves the heating-up of the containment heat transfer plate. An inverse heat conduction model was developed to capture the rapid transient transfer characteristics, and the analysis method is applicable to SMR safety analysis. (2) The average condensation heat transfer coefficients for different pressure conditions and non-condensable gas mass fractions were obtained from the integral test facility, through the measurements of the heat conduction rate across the containment heat transfer plate, and from the water condensation rates measurement based on the total energy balance equation. 15 (3) The test results using the measured HTP wall temperatures are considerably lower than popular condensation models would predict mainly due to the side wall conduction effects in the existing MASLWR integral test facility. The data revealed the detailed heat transfer characteristics of the model containment, important to the SMR safety analysis and the validation of associated evaluation model. However this approach, unlike separate effect tests, cannot isolate the condensation heat transfer coefficient over the containment wall, and therefore is not suitable for the assessment of the condensation heat transfer coefficient against system pressure and noncondensable ...
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 225
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Book Description
This NEUP funded project, NEUP 12-3630, is for experimental, numerical and analytical studies on high-pressure steam condensation phenomena in a steel containment vessel connected to a water cooling tank, carried out at Oregon State University (OrSU) and the University of Wisconsin at Madison (UW-Madison). In the three years of investigation duration, following the original proposal, the planned tasks have been completed: (1) Performed a scaling study for the full pressure test facility applicable to the reference design for the condensation heat transfer process during design basis accidents (DBAs), modified the existing test facility to route the steady-state secondary steam flow into the high pressure containment for controllable condensation tests, and extended the operations at negative gage pressure conditions (OrSU). (2) Conducted a series of DBA and quasi-steady experiments using the full pressure test facility to provide a reliable high pressure condensation database (OrSU). (3) Analyzed experimental data and evaluated condensation model for the experimental conditions, and predicted the prototypic containment performance under accidental conditions (UW-Madison). A film flow model was developed for the scaling analysis, and the results suggest that the 1/3 scaled test facility covers large portion of laminar film flow, leading to a lower average heat transfer coefficient comparing to the prototypic value. Although it is conservative in reactor safety analysis, the significant reduction of heat transfer coefficient (50%) could under estimate the prototypic condensation heat transfer rate, resulting in inaccurate prediction of the decay heat removal capability. Further investigation is thus needed to quantify the scaling distortion for safety analysis code validation. Experimental investigations were performed in the existing MASLWR test facility at OrST with minor modifications. A total of 13 containment condensation tests were conducted for pressure ranging from 4 to 21 bar with three different static inventories of non-condensable gas. Condensation and heat transfer rates were evaluated employing several methods, notably from measured temperature gradients in the HTP as well as measured condensate formation rates. A detailed mass and energy accounting was used to assess the various measurement methods and to support simplifying assumptions required for the analysis. Condensation heat fluxes and heat transfer coefficients are calculated and presented as a function of pressure to satisfy the objectives of this investigation. The major conclusions for those tests are summarized below: (1) In the steam blow-down tests, the initial condensation heat transfer process involves the heating-up of the containment heat transfer plate. An inverse heat conduction model was developed to capture the rapid transient transfer characteristics, and the analysis method is applicable to SMR safety analysis. (2) The average condensation heat transfer coefficients for different pressure conditions and non-condensable gas mass fractions were obtained from the integral test facility, through the measurements of the heat conduction rate across the containment heat transfer plate, and from the water condensation rates measurement based on the total energy balance equation. 15 (3) The test results using the measured HTP wall temperatures are considerably lower than popular condensation models would predict mainly due to the side wall conduction effects in the existing MASLWR integral test facility. The data revealed the detailed heat transfer characteristics of the model containment, important to the SMR safety analysis and the validation of associated evaluation model. However this approach, unlike separate effect tests, cannot isolate the condensation heat transfer coefficient over the containment wall, and therefore is not suitable for the assessment of the condensation heat transfer coefficient against system pressure and noncondensable ...
Author: Francesco D'Auria
Publisher: Elsevier
ISBN: 0323856098
Category : Technology & Engineering
Languages : en
Pages : 818
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Book Description
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 3, Procedures and Applications includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix Covers applicable nuclear reactor safety considerations and design technology throughout
Author: Dhongik Samuel Yoon
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Condensation of steam vapor is an important mode of energy removal from the reactor containment in postulated design basis accidents where high-energy steam escapes into the reactor containment. Due to its passive nature and magnitude of heat transfer associated with phase change, condensation can be used as an effective energy removal mechanism, especially for reactors with a passive containment cooling system. Therefore, there has been a great interest in modeling condensation phenomena in the reactor containment for the purpose of accident analysis. Until recently, the focus has been the presence of noncondensable gas since traditional reactor designs operate at near atmospheric pressure with substantial amount of noncondensable gas in the containment, which hinders the process of condensation heat transfer. In this case, the phase change is dominated by diffusion resistance in the gas mixture phase and the thermal resistance of condensate film layer can be neglected. Recent advanced reactor designs, on the other hand, are designed to allow very low air pressure in the containment. In this case, the heat transfer resistance due to the presence of noncondensable gas is reduced significantly and the thermal resistance of condensate film layer can no longer be neglected. Moreover, it has been reported that condensation on the micro or nano-engineered surfaces shows substantially different behavior compared to traditional untreated surfaces. Those engineered surfaces with modified wetting characteristics can affect the condensation rates by affecting the condensate film behavior on such surfaces, proposing a potential way of affecting the heat removal from reactor containment by wall surface modification. Consequently, it has become relevant and necessary to study and characterize the effect of thermal resistance and kinetic conditions of the condensate film layer on the overall condensation heat transfer in the reactor containment regarding conditions with very low noncondensable gas concentration where the presence of condensate film layer can no longer be neglected. The current condensation model in MELCOR was evaluated in order to assess its capability to predict condensation heat transfer for traditional containment conditions. By modeling sets of containment condensation experiments, satisfactory performance of MELCOR in predicting condensation phenomena was confirmed for conditions with significant noncondensable gas concentration. It has to be noted that, as a result of this assessment, few adjustments has been implemented to guarantee more accurate predictions of MELCOR in specific conditions addressed in those experiments. However, it is observed that MELCOR may be inaccurate in predicting condensation for conditions with very low noncondensable gas concentrations where the effects of condensate film layer is more prominent. However, MELCOR's correlation-based models prevent further investigations on the parameters that have not been already implemented. In an effort to better understand the effect of thermal resistance and kinetic conditions of the condensate film layer for conditions with very low noncondensable gas concentrations, a condensation model was developed in the framework of a Computation Fluid Dynamics (CFD) to include thermal and kinetic conditions of the condensate film layer. The developed condensation model includes heat transfer resistances in both phases without directly simulating the two-fluid problem and proposes that the liquid-gas interface can be represented as a free surface. Case studies were conducted to show its theoretical validity. The developed condensation model including the thermal resistance of the condensate film layer and the free surface assumption was validated against two sets of separate effects experiments, one in traditional reactor containment conditions and the other in a pure steam condition. The results indicate that a free surface assumption can greatly improve the prediction of condensation heat transfer, even for traditional reactor containment conditions where the concentration of noncondensable gas is significant. Including the thermal resistance of the condensate film layer does not provide a significant change in the results for high noncondensable gas concentration cases, as expected. For near-pure steam conditions, however, the effect of the condensate film is not only significant but also increases with decreasing noncondensable gas concentration as expected. The proposed modeling approach is also able to account for this effect.
Author: Palash Kumar Bhowmik
Publisher:
ISBN:
Category :
Languages : en
Pages : 199
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Book Description
"The purpose of this research was to perform scaled experiments and simulations to validate computational fluid dynamics (CFD) and empirical models of condensation heat transfer (CHT) for the passive containment cooling system (PCCS) of Small Modular Reactors (SMRs). SMRs are the futuristic candidates for clean, economic, and safe energy generation; however, reactor licensing requires safety system evaluations, such as PCCS. The knowledge in the reviewed relevant literature showed a gap in experimental data for scaling SMR's safety systems and validating computational models. The previously available test data were inconsistent due to unscaled geometric and varying physics conditions. These inconsistencies lead to inadequate test data benchmarking. This study developed three scaled (different diameters) test sections with annular cooling for scale testing and analysis to fill this research gap. First, tests were performed for pure steam and steam with non-condensable gases (NCGs), like nitrogen and helium, at different mass fractions, inlet mass flow rates, and pressure ranges. Second, detailed CFD simulations and validations were performed using STAR-CCM+ software with scaled geometries and experimental parameters (e.g., flow rate, pressure, and steam-NCG mixtures), thus mimicking reactor accident cases. The multi-component gases, multiphase mixtures, and fluid film condensation models were applied, verified, and optimized in the CFD simulations with associated turbulence models. Third, the physics-based and data-driven condensation models and empirical correlations were assessed to quantify the scaling distortions. Finally, the experiments, simulations, and modeling results were evaluated for critical insights into the physics conditions, scaling effects, and multi-component gas mixture parameters. This study supported improvements to nuclear reactor safety systems' modeling capabilities irrespective of size (small or big), and findings were equally applicable to other non-nuclear energy applications"--Abstract, page iii.
Author: Dongyoung Lee
Publisher:
ISBN:
Category : Condensation
Languages : en
Pages : 132
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Book Description
There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and Tsunami with the height of 15 m on March 11, 2011. Small Modular Reactors (SMRs) have been developed to improve safety systems by utilizing passive and natural circulation forces under normal operations and accident conditions. One key feature of the safety systems in SMRs is the use of containment condensation to prevent core melt down. For further development of the SMR for design certifications, the condensation model at relatively high pressures compared with current operating power plants should be verified and validated. For this process, at Oregon State University, the MASLWR (Multi Application Small Light Water Reactor) test facility, which has 1:3 length scale, can perform integrated tests on containment condensation of SMRs. Using the MASLWR test facility experimental data, this study investigated three major subjects: heat flux estimation on the containment wall, flow transition of condensation film flow dynamics and assessing the scaling effects of the MASLWR test facility. An inverse heat conduction algorithm was developed to estimate the heat fluxes of film condensation at the containment wall in the MASLWR test facility during transients. Through a fundamental one-dimensional approach for condensation film flow, the governing equations were derived and numerically solved. A linear perturbation stability analysis using steady-state results of condensation film flow at the containment wall found that Re ~1600 is the transition point between laminar and turbulent film flow regimes. This finding agreed with the experimental results of Ishigai et al. (1974) and Morioka et al. (1993). Based on scaling analysis using the diffusion layer model and experimental correlations, the length distortion factor was examined. In this study, it was found that the 1:3 length scale test facility underestimated the heat transfer rate more than the prototype. The results presented in this dissertation cover the film flow dynamics of condensation film flows as well as an inverse heat transfer calculation to advance the knowledge of containment condensation in SMRs.
Author: Jun Wang
Publisher: Woodhead Publishing
ISBN: 0128181915
Category : Technology & Engineering
Languages : en
Pages : 612
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Book Description
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 324
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Book Description
Author: Jyeshtharaj Joshi
Publisher: Woodhead Publishing
ISBN: 0081023375
Category : Science
Languages : en
Pages : 888
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Book Description
Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization
Author: Daniel T. Ingersoll
Publisher: Woodhead Publishing
ISBN: 0128239174
Category : Technology & Engineering
Languages : en
Pages : 648
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Book Description
Handbook of Small Modular Nuclear Reactors, Second Edition is a fully updated comprehensive reference on Small Modular Reactors (SMRs), which reflects the latest research and technological advances in the field from the last five years. Editors Daniel T. Ingersoll and Mario D. Carelli, along with their team of expert contributors, combine their wealth of collective experience to update this comprehensive handbook that provides the reader with all required knowledge on SMRs, expanding on the rapidly growing interest and development of SMRs around the globe. This book begins with an introduction to SMRs for power generation, an overview of international developments, and an analysis of Integral Pressurized Water Reactors as a popular class of SMRs. The second part of the book is dedicated to SMR technologies, including physics, components, I&C, human-system interfaces and safety aspects. Part three discusses the implementation of SMRs, covering economic factors, construction methods, hybrid energy systems and licensing considerations. The fourth part of the book provides an in-depth analysis of SMR R&D and deployment of SMRs within eight countries, including the United States, Republic of Korea, Russia, China, Argentina, and Japan. This edition includes brand new content on the United Kingdom and Canada, where interests in SMRs have increased considerably since the first edition was published. The final part of the book adds a new analysis of the global SMR market and concludes with a perspective on SMR benefits to developing economies. This authoritative and practical handbook benefits engineers, designers, operators, and regulators working in nuclear energy, as well as academics and graduate students researching nuclear reactor technologies. Presents the latest research on SMR technologies and global developments Includes new case study chapters on the United Kingdom and Canada and a chapter on global SMR markets Discusses new technologies such as floating SMRs and molten salt SMRs
Author: Moo Hwan Kim
Publisher:
ISBN:
Category : Condensation
Languages : en
Pages : 552
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Book Description
