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Modelling Candu Fuel Under Normal Operating Conditions Elestres Code Description
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Book Synopsis Modelling CANDU fuel under normal operating conditions : elestres code description by : M. Tayal
Download or read book Modelling CANDU fuel under normal operating conditions : elestres code description written by M. Tayal and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of three experiments, simulating outlet header breaks followed by emergency coolant injection, has been performed with the rd-12 loop. the loop had two heated sections in parallel in each pass during these experiments. the heating elements were the indirectly heated type with heat storage capacity similar to that of candu reactor fuel rods. the tests were performed with break orifice areas equal to 34 percent, 40 percent and 46 percent of the feeder cross-sectional area. the primary circulating pumps were kept running throughout each experiment. extended periods of very low or zero liquid flow in the intact pass were observed in all three experiments. with 40 percent and 46 percent break orifices, the low flows resulted in heater sheath temperature excursions to the trip set point of 800 degrees c. the present report briefly reviews the experimental results and provides a complete set of measured parameters. this work was funded jointly by atomic energy of canada limited and ontario hydro under the candev program.
Book Synopsis Elestres : modelling of fuel element behaviour under normal operating conditions by : H. H. Wong
Download or read book Elestres : modelling of fuel element behaviour under normal operating conditions written by H. H. Wong and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Elestres is a computer code designed to model the behaviour of candu nuclear fuel elements under normal operating conditions. the aim of this report is to provide the reader with a perspective of the modelling processes involved within elestres in the prediction of fuel behaviour. it is not intended as a user's manual or a code verification document. emphasis is therefore placed on a discussion of the nature of the problem, the approximations and the numerical methods used, and how the various fuel behaviour models are combined to give the predictive capability in elestres.
Book Synopsis A Thermomechanical Model of CANDU Fuel by : Daniel Morgan
Download or read book A Thermomechanical Model of CANDU Fuel written by Daniel Morgan and published by . This book was released on 2007 with total page 191 pages. Available in PDF, EPUB and Kindle. Book excerpt: A fundamental code for predicting CANDU nuclear fuel thermomechanical behaviour in normal operating conditions was developed with the use of the Comsol Multiphysics finite element modelling environment. The code predicts the thermal response of the fuel, fuel thermal expansion, irradiation-induced densification, fission product swelling, fission gas release, and elastic and plastic deformation of the fuel and cladding. The evolution of the fuel-to-clad gap was predicted using the overall deformation of the fuel and sheath. The code was able to predict the behaviour of fuel under normal operating conditions and has been benchmarked against the industry-standard ELESTRES-IST fuel performance code.
Book Synopsis Fundamentals of Nuclear Engineering by : Brent J. Lewis
Download or read book Fundamentals of Nuclear Engineering written by Brent J. Lewis and published by John Wiley & Sons. This book was released on 2017-03-24 with total page 984 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fundamental of Nuclear Engineering is derived from over 25 years of teaching undergraduate and graduate courses on nuclear engineering. The material has been extensively class tested and provides the most comprehensive textbook and reference on the fundamentals of nuclear engineering. It includes a broad range of important areas in the nuclear engineering field; nuclear and atomic theory; nuclear reactor physics, design, control/dynamics, safety and thermal-hydraulics; nuclear fuel engineering; and health physics/radiation protection. It also includes the latest information that is missing in traditional texts, such as space radiation. The aim of the book is to provide a source for upper level undergraduate and graduate students studying nuclear engineering.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-12 with total page 508 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Element leaching and capillary rise in sandy soil cores : experimental results by : M. I. Sheppard
Download or read book Element leaching and capillary rise in sandy soil cores : experimental results written by M. I. Sheppard and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Elestres.m9d is a fuel performance code designed to predict the behaviour of candu fuel under normal operating conditions. it has, in common with elesim, one dimensional models of heat generation, temperature distribution, fission gas release and fuel to sheath heat transfer. it is different from elesim in that a two-dimensional axisymmetric stress-strain analysis on the fuel pellet is performed using the finite element method. this report is intended as a user's manual and detailed code description of elestres. it includes a short description of the capabilities of the code and detailed input instructions for the general user. for the code developer, a detailed description of the program layout, the mathematical models used, the source listing and the nomenclature are included in later sections of the report. the report is not intended as a description of the theory behind the models, and the reader should consult the appropriate references for that purpose.
Author :Atomic Energy of Canada Limited Publisher :Chalk River, Ontario : Chalk River Laboratories ISBN 13 : Total Pages :13 pages Book Rating :4.:/5 (225 download)
Book Synopsis Survey of Tritiated Oil Sources and Handling Practices [electronic Resource] by : Atomic Energy of Canada Limited
Download or read book Survey of Tritiated Oil Sources and Handling Practices [electronic Resource] written by Atomic Energy of Canada Limited and published by Chalk River, Ontario : Chalk River Laboratories. This book was released on 1994 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the 12th Pacific Rim Conference on Ceramic and Glass Technology by : Dileep Singh
Download or read book Proceedings of the 12th Pacific Rim Conference on Ceramic and Glass Technology written by Dileep Singh and published by John Wiley & Sons. This book was released on 2018-04-19 with total page 358 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ceramic Transactions, Volume 264, Proceedings of the 12th Pacific Rim Conference on Ceramic and Glass Technology Dileep Singh, Manabu Fukushima, Young-Wook Kim, Kiyoshi Shimamura, Nobuhito Imanaka, Tatsuki Ohji, Jake Amoroso, and Michael Lanagan; Editors This proceedings contains a collection of 32 papers presented at the 12th Pacific Rim Conference on Ceramic and Glass Technology (PacRim12), May 21-26, 2017 in Waikoloa, Hawaii. PacRim is a bi-annual conference held in collaboration with the ceramic societies of the Pacific Rim countries - The American Ceramic Society, The Chinese Ceramic Society, The Korean Ceramic Society, and the Australian Ceramic Society. Topics included in this collection include multiscale modeling and simulation, processing and manufacturing, nanotechnology, multifunctional materials, ceramics for energy and the environment, biomedical materials, and more
Book Synopsis Elestres.m9d user's manual and code description. (update.1 to version m9c). by : E. Alp
Download or read book Elestres.m9d user's manual and code description. (update.1 to version m9c). written by E. Alp and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Elestres.m9d is a fuel performance code designed to predict the behaviour of candu fuel under normal operating conditions. it has, in common with elesim, one dimensional models of heat generation, temperature distribution, fission gas release and fuel to sheath heat transfer. it is different from elesim in that a two-dimensional axisymmetric stress-strain analysis on the fuel pellet is performed using the finite element method. this report is intended as a user's manual and detailed code description of elestres. it includes a short description of the capabilities of the code and detailed input instructions for the general user. for the code developer, a detailed description of the program layout, the mathematical models used, the source listing and the nomenclature are included in later sections of the report. the report is not intended as a description of the theory behind the models, and the reader should consult the appropriate references for that purpose.
Book Synopsis Influence of heat treatment and redox conditions on crystallization of titanosilicate glass-ceramics by : P. J. Hayward
Download or read book Influence of heat treatment and redox conditions on crystallization of titanosilicate glass-ceramics written by P. J. Hayward and published by . This book was released on 1986 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Elestres is a computer code designed to model the behaviour of candu nuclear fuel elements under normal operating conditions. the aim of this report is to provide the reader with a perspective of the modelling processes involved within elestres in the prediction of fuel behaviour. it is not intended as a user's manual or a code verification document. emphasis is therefore placed on a discussion of the nature of the problem, the approximations and the numerical methods used, and how the various fuel behaviour models are combined to give the predictive capability in elestres.
Book Synopsis 4th International Conference on CANDU Fuel by :
Download or read book 4th International Conference on CANDU Fuel written by and published by . This book was released on 1995 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Loss-of-coolant Accident Analysis for Near Stagnation Flow in the Horizontal Fuel Channel of Candu Reactor by : Ahmet Durmayaz
Download or read book A Loss-of-coolant Accident Analysis for Near Stagnation Flow in the Horizontal Fuel Channel of Candu Reactor written by Ahmet Durmayaz and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In this thesis, a two-phase thermalhydraulic model has been developed inorder to investigate the near stagnation flow phenomena in the horizontal fuelchannel of a CANDU nuclear reactor following a postulated small break _loss-_of-çoolant-accident (LOCA) in the inlet feeder or inlet header. In this model, the unequal velocity unequal temperature (UVUT) modelis used in which the velocities and enthalpies (hence temperatures) for both liquidand vapor phases, void fraction and a common dynamic pressure are computed. Stratified smooth and dispersed bubbly flows are considered together for the near stagnation flow and dispersed bubbly flow is considered for the normal operating conditions of a CANDU reactor as the flow regimes. Geometrical configuration of a typically CANDU reactor fuel channel is considered. Thermodynamic andtransport properties of heavy water are also considered as functions of pressure and temperature. In the derivations of the conservation equations, all of the terms are area and time (ensemble) averaged. A fully implicit discretization method and a staggered grid control volume approach are applied in order to obtain an algebraic equation set from the governing differential conservation equations. Hvbrid scheme. in which central difference and upwind schemes are considered by turns depending on the value of Peclet number, is used while deriving the discretization equations. To solve the near stagnation flow problem by using this model, the IPSA algorithm (Inter-Phase Slip Algorithm) which was developed to solve the multi-phase flows originally is modified to give a solution for a horizontal channel which is full of single phase fluid in some part whereas it is full of two- phase fluid in the other part. A computer code that is called as the ANESTA ( Analysis for NEar STAgnation flow in the fuel channel of a CANDU reactor ) code has been developed. The model mentioned above is applied to both normal operating conditions and the near stagnation flow (LOCA) conditions by this code. A set of approximate functions for the fast calculation of the thermodynamic properties of heavy water (D20 ) has also been derived. For this aim, the data given in the steam tables for heavy water thermodynamic properties have been accurately and successfully fitted to the curves as functions of pressure and temperature in order to obtain some simple functions by usingthe least-square method.
Author : Publisher :Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development ISBN 13 : Total Pages :572 pages Book Rating :4.3/5 (91 download)
Book Synopsis Fission Gas Behaviour in Water Reactor Fuels by :
Download or read book Fission Gas Behaviour in Water Reactor Fuels written by and published by Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development. This book was released on 2002 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt: Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Book Synopsis Encyclopedia of CANDU fuel under normal operating conditions by : M. J. F. Notley
Download or read book Encyclopedia of CANDU fuel under normal operating conditions written by M. J. F. Notley and published by . This book was released on 1988 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Technical Reports Series written by and published by . This book was released on 2002 with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :Arimescu, V. I Publisher :Chalk River, Ont. : Fuel Engineering Branch, Chalk River Laboratories ISBN 13 : Total Pages :22 pages Book Rating :4.:/5 (268 download)
Book Synopsis Modeling CANDU-type Fuel Behaviour During Extended Burnup Irradiations Using a Revised Version of the ELESIM Code by : Arimescu, V. I
Download or read book Modeling CANDU-type Fuel Behaviour During Extended Burnup Irradiations Using a Revised Version of the ELESIM Code written by Arimescu, V. I and published by Chalk River, Ont. : Fuel Engineering Branch, Chalk River Laboratories. This book was released on 1992 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A computer program for modelling CANDU - fuel element performance by : J. A. Middleton
Download or read book A computer program for modelling CANDU - fuel element performance written by J. A. Middleton and published by . This book was released on 1975 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Much experimental information is available on the performance of uo2 fuel elements, some of which has been interpreted in terms of simple mathematical models. however, because of the interaction between experimental variables it is often difficult to identify the correlation between causes and effects; and it becomes necessary to identify the most probable cause by numerical evaluation of the effects of competing phenomena. numerical evaluation techniques for predicting fuel element performance are obviously useful in guiding fuel design, but at our present stage of development cannot replace proof testing or experimental investigations; rather, numerical evaluation should proceed along with experimental work, each throwing some insight into the physical processes in the system under study. a general description of the computer program to simulate fuel performance and the experimental data against which it was assessed has been given in reference(1); the purpose of the present report is to give a detailed breakdown of the logic and the way it is incorporated in the program, and to be a guide for potential users. readers are therefore advised to first read reference(1) to acquire a more general idea of the limitations and capabilities of the program. the program is written in fortran specifically for use on the crnl - cdc - 6600 computer. it predicts quantities such as sheath strain (due primarily to fuel thermal expansion, not swelling), fission product gas release and the resultant internal gas pressure, the possible effect of internal gas pressure on fuel-clad interfacial pressure and hence heat transfer, stress and strain in the clad, and the overall interactions of these variables to give the final quantities of interest; fuel temperatures, clad strain and fission product gas release. possible interactions are represented diagrammatically in figure 1, and described more thoroughly in the text following.
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