Modeling of Natural Circulation Phenomena in Nuclear Reactor Cooling Loops

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (952 download)

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Book Synopsis Modeling of Natural Circulation Phenomena in Nuclear Reactor Cooling Loops by :

Download or read book Modeling of Natural Circulation Phenomena in Nuclear Reactor Cooling Loops written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Natural Circulation in Water Cooled Nuclear Power Plants

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Publisher : IAEA
ISBN 13 :
Total Pages : 656 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Natural Circulation in Water Cooled Nuclear Power Plants by : International Atomic Energy Agency

Download or read book Natural Circulation in Water Cooled Nuclear Power Plants written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 656 pages. Available in PDF, EPUB and Kindle. Book excerpt: Describes the state of knowledge of natural circulation in water cooled nuclear power plants and passive system reliability. The publication presents information on phenomena, models, predictive tools and experiments that currently support design and analysis of natural circulation systems, and highlights areas where additional research is needed.

Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors

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ISBN 13 : 9789201274106
Total Pages : 423 pages
Book Rating : 4.2/5 (741 download)

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Book Synopsis Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors by : International Atomic Energy Agency

Download or read book Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 423 pages. Available in PDF, EPUB and Kindle. Book excerpt: Based on an IAEA coordinated research project focused on the use of passive safety systems and natural circulation to help meet the safety and economic goals of advanced nuclear power plants, this publication includes the identification and definition of the thermo-hydraulic phenomena that affect the reliability of passive safety systems, characterization of each phenomenon, integral tests to examine the passive systems and natural circulation, and a methodology for examining passive system reliability.

Simulation Experiments on Two-phase Natural Circulation in a Freon-113 Flow Visualization Loop

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ISBN 13 :
Total Pages : 66 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Simulation Experiments on Two-phase Natural Circulation in a Freon-113 Flow Visualization Loop by : Sang-Yong Lee

Download or read book Simulation Experiments on Two-phase Natural Circulation in a Freon-113 Flow Visualization Loop written by Sang-Yong Lee and published by . This book was released on 1988 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Natural Circulation Phenomena in Nuclear Reactor Systems

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ISBN 13 :
Total Pages : 80 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Natural Circulation Phenomena in Nuclear Reactor Systems by : F. B. Cheung

Download or read book Natural Circulation Phenomena in Nuclear Reactor Systems written by F. B. Cheung and published by . This book was released on 1994 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Single-phase, Two-phase and Supercritical Natural Circulation Systems

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Publisher : Woodhead Publishing
ISBN 13 : 0081024878
Total Pages : 650 pages
Book Rating : 4.0/5 (81 download)

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Book Synopsis Single-phase, Two-phase and Supercritical Natural Circulation Systems by : Pallippattu Krishnan Vijayan

Download or read book Single-phase, Two-phase and Supercritical Natural Circulation Systems written by Pallippattu Krishnan Vijayan and published by Woodhead Publishing. This book was released on 2019-06-19 with total page 650 pages. Available in PDF, EPUB and Kindle. Book excerpt: Single-Phase, Two-Phase and Supercritical Natural Circulation Systems provides readers with a deep understanding of natural circulation systems. This book equips the reader with an understanding on how to detect unstable loops to ensure plant safety and reliability, calculate heat transport capabilities, and design effective natural circulation loops, stability maps and parallel channel systems. Each chapter begins with an introduction to the circulation system before discussing each element in detail and analyzing its effect on the performance of the system. The book also presents thermosyphon heat transport devices in nuclear and other industrial plants, a common information need for students and researchers alike. This book is invaluable for engineers, designers, operators and consultants in nuclear, mechanical, electrical and chemical disciplines. Presents single-phase, two-phase and supercritical natural circulation systems together in one resource to fill an existing knowledge gap Guides the reader through relevant processes, such as designing, analyzing and generating stability maps and natural circulation loops, calculating heat transport capabilities, and maintaining natural circulation system operations Includes global case studies and examples to increase understanding, along with important IAEA standards and procedures

Design of Complex Systems to Achieve Passive Safety

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ISBN 13 :
Total Pages : 352 pages
Book Rating : 4.:/5 (839 download)

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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.

On the Stability of Natural Circulation Loops with Phase Change

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (969 download)

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Book Synopsis On the Stability of Natural Circulation Loops with Phase Change by : Troy Christopher Haskin

Download or read book On the Stability of Natural Circulation Loops with Phase Change written by Troy Christopher Haskin and published by . This book was released on 2016 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The stability of a simple, closed-loop, water-cooled natural circulation system was characterized over a range of single phase and two-phase states. The motivation for this investigation is a Next Generation Nuclear Plant safety cooling system called the Reactor Cavity Cooling System (RCCS). One of the proposed designs for the RCCS is a closed-circuit of network piping using water as a working fluid. One of the safety considerations for such a system is the stability of the system at steady-state under a large number of unknown states. This work provides a derivation of the commonly used one-dimensional conservation laws used in thermohydraulic system modeling and a novel discretization scheme that allows for exact integration of the computational domain for accurate calculation of eigenvalues of a linearized system. The steady-state solution of the discretized equations is then performed using a fully nonlinear Jacobian-Free Newton Krylov Method for a number of temperatures, pressures, and heat loads both in single and two-phase conditions. All of the single and two-phase state exhibit linear stability to small perturbations in values. The linear stability is also found to increase with increasing heat load due to the greater inertia of the system damping out small perturbation effectively and with increasing pressure due to the greater stiffness of the fluid. Nonlinear stability was also examined for a point power insertion of varying intensity from two steady-states. The loop exhibited stability for all power insertions from both steady-states, returning to the initial steady value shortly after the pulse.

Thermal-Hydraulics of Water Cooled Nuclear Reactors

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Publisher : Woodhead Publishing
ISBN 13 : 0081006799
Total Pages : 1200 pages
Book Rating : 4.0/5 (81 download)

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Book Synopsis Thermal-Hydraulics of Water Cooled Nuclear Reactors by : Francesco D'Auria

Download or read book Thermal-Hydraulics of Water Cooled Nuclear Reactors written by Francesco D'Auria and published by Woodhead Publishing. This book was released on 2017-05-18 with total page 1200 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

Energy Research Abstracts

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Publisher :
ISBN 13 :
Total Pages : 526 pages
Book Rating : 4.0/5 ( 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 1994-04 with total page 526 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs

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Publisher : IOS Press
ISBN 13 : 9781586036058
Total Pages : 148 pages
Book Rating : 4.0/5 (36 download)

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Book Synopsis Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs by : Masahiro Furuya

Download or read book Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs written by Masahiro Furuya and published by IOS Press. This book was released on 2006 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt: 20% of the Nuclear Power Plants are known as Boiling Water Reactors (BWRs). These BWRs have pumps that cool their reactor. In the design of new BWRs, ways to cool the core by a natural circulation flow, without pumps, also called natural circulation BWRs, are being considered. In these new systems, a chimney is installed on top of the core to increase natural circulation flow. A possible disadvantage of natural circulation BWRs might be their susceptibility to instabilities, which could then lead to both flow and power oscillations. The stability features of both natural circulation and forced circulation BWRs have been investigated thoroughly, using dedicated experimental setups, analytical models and numerical codes. We distinguish between pure thermal-hydraulic stability - where the fission power is assumed to be constant - and coupled thermalhydraulic-neutronic stability - where the two-phase mixture in the core influences the fission chain reaction...

Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors

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Publisher :
ISBN 13 :
Total Pages : 58 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors by : Chathilingath K. Sanathanan

Download or read book Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors written by Chathilingath K. Sanathanan and published by . This book was released on 1964 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt: The dynamics of two-phase flow through the coolant channels of a natural-circulation boiling water nuclear reactor is studied analytically. One-dimensional conservation equations describing the flow through each channel are written in a linearized perturbed form, and Laplace transformation in time is performed. A systematic procedure is developed to approximate the solution. The solution may be oscillatory both in time and space, and the stability depends largely upon the steady-state profile of velocity and void fraction along the channel, as well as the channel length. The simplifying assumption made by earlier investigators that the slip ratio is constant along the channel length is shown to yield results close to the true solution.

ERDA Energy Research Abstracts

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ISBN 13 :
Total Pages : 1028 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis ERDA Energy Research Abstracts by :

Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1983 with total page 1028 pages. Available in PDF, EPUB and Kindle. Book excerpt:

ANS Proceedings

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ISBN 13 :
Total Pages : 264 pages
Book Rating : 4.0/5 ( download)

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Book Synopsis ANS Proceedings by :

Download or read book ANS Proceedings written by and published by . This book was released on 1987 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Fluid Mechanics and Fluid Power (Vol. 3)

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Publisher : Springer Nature
ISBN 13 : 9811962707
Total Pages : 628 pages
Book Rating : 4.8/5 (119 download)

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Book Synopsis Fluid Mechanics and Fluid Power (Vol. 3) by : Suvanjan Bhattacharyya

Download or read book Fluid Mechanics and Fluid Power (Vol. 3) written by Suvanjan Bhattacharyya and published by Springer Nature. This book was released on 2023-04-17 with total page 628 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book presents the select proceedings of the 48th National Conference on Fluid Mechanics and Fluid Power (FMFP 2021) held at BITS Pilani in December 2021. It covers the topics such as fluid mechanics, measurement techniques in fluid flows, computational fluid dynamics, instability, transition and turbulence, fluid‐structure interaction, multiphase flows, micro- and nanoscale transport, bio-fluid mechanics, aerodynamics, turbomachinery, propulsion and power. The book will be useful for researchers and professionals interested in the broad field of mechanics.

MODELING STRATEGIES TO COMPUTE NATURAL CIRCULATION USING CFD IN A VHTR AFTER A LOFA

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (16 download)

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Book Synopsis MODELING STRATEGIES TO COMPUTE NATURAL CIRCULATION USING CFD IN A VHTR AFTER A LOFA by :

Download or read book MODELING STRATEGIES TO COMPUTE NATURAL CIRCULATION USING CFD IN A VHTR AFTER A LOFA written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A prismatic gas-cooled very high temperature reactor (VHTR) is being developed under the next generation nuclear plant program (NGNP) of the U.S. Department of Energy, Office of Nuclear Energy. In the design of the prismatic VHTR, hexagonal shaped graphite blocks are drilled to allow insertion of fuel pins, made of compacted TRISO fuel particles, and coolant channels for the helium coolant. One of the concerns for the reactor design is the effects of a loss of flow accident (LOFA) where the coolant circulators are lost for some reason, causing a loss of forced coolant flow through the core. In such an event, it is desired to know what happens to the (reduced) heat still being generated in the core and if it represents a problem for the fuel compacts, the graphite core or the reactor vessel (RV) walls. One of the mechanisms for the transport of heat out of the core is by the natural circulation of the coolant, which is still present. That is, how much heat may be transported by natural circulation through the core and upwards to the top of the upper plenum? It is beyond current capability for a computational fluid dynamic (CFD) analysis to perform a calculation on the whole RV with a sufficiently refined mesh to examine the full potential of natural circulation in the vessel. The present paper reports the investigation of several strategies to model the flow and heat transfer in the RV. It is found that it is necessary to employ representative geometries of the core to estimate the heat transfer. However, by taking advantage of global and local symmetries, a detailed estimate of the strength of the resulting natural circulation and the level of heat transfer to the top of the upper plenum is obtained.

Transient Analysis of Emergency Cooling Systems for Submarine Nuclear Reactors

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ISBN 13 :
Total Pages : 258 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Transient Analysis of Emergency Cooling Systems for Submarine Nuclear Reactors by : H. A. Harrington

Download or read book Transient Analysis of Emergency Cooling Systems for Submarine Nuclear Reactors written by H. A. Harrington and published by . This book was released on 1959 with total page 258 pages. Available in PDF, EPUB and Kindle. Book excerpt: