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A Computer Program For Modelling Candu Fuel Element Performance
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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.
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 Comprehensive Nuclear Materials by :
Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Book Synopsis Canadian Fuel Development Program by :
Download or read book Canadian Fuel Development Program written by and published by . This book was released on 1992 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper reviews some of the key programs on fuel technology within the CANDU power reactor owners' group. It begins with outlining the characteristics and design evolution of CANDU power reactor fuel, its performance, and defect mechanisms. The paper reviews the programs in two groups: the Fuel Technology Program and the Advanced Fuel Cycle programs. Key elements in these programs include studies of the effect of oxygen/metal ratio on fuel performance, corrosion protection, extended burnup irradiation, operational limits, fuel damage, fuel behavior modelling, decay heat removal, and the use of recovered uranium, spent pressurized-water reactor fuel, and low void reactivity fuel.
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:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 658 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 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 2017-03-31 with total page 1233 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.
Book Synopsis Experimental and numerical studies on liquid metal cooled fast reactors by : Songbai Cheng
Download or read book Experimental and numerical studies on liquid metal cooled fast reactors written by Songbai Cheng and published by Frontiers Media SA. This book was released on 2023-03-03 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Generic aspects of CANDU fuel element performance during normal operation by : M. J. F. Notley
Download or read book Generic aspects of CANDU fuel element performance during normal operation written by M. J. F. Notley and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindex written by and published by . This book was released on 1986 with total page 1324 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Generic aspects of CANDU fuel element performance during normal operation by : I. J. Hastings
Download or read book Generic aspects of CANDU fuel element performance during normal operation written by I. J. Hastings and published by . This book was released on 1989 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1977 with total page 800 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1983 with total page 738 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.
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 Comparison between data from the CANDU/pbf loca test and calculations by the fuel performance code for accident analysis, eloca by : J. A. Walsworth
Download or read book Comparison between data from the CANDU/pbf loca test and calculations by the fuel performance code for accident analysis, eloca written by J. A. Walsworth and published by . This book was released on 1985 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Three pre-irradiated (120 mw.h/kg u) and one fresh bruce-size, candu fuel elements were simultaneously subjected to a coolant depressurization transient in the power burst facility (pbf) at the idaho national engineering laboratory (inel) in idaho falls, u.s.a. a feature of the test was the ability of the pbf to control fuel element powers during depressurization. the elements were subjected to a brief power pulse just prior to decay power level. the magnitude and duration of the power pulse and the rate of depressurization were selected to be typical of expected conditions in a candu reactor during a large break loss-of-coolant accident. all four fuel element assemblies were instrumented to measure coolant and fuel response during the test. comparisons between qualified data and calculations by the eloca.mk4 computer code have been made for several parameters including sheath strain, the mechanisms and timing of element failure, internal element gas pressure, fuel centreline temperature, sheath microstructure, and thickness of zirconia and oxygen-stabilized alpha-zr layers on the sheaths. results from post-test profilometry and sheath strain calculations are in good agreement. mechanical response of the sheaths was not significantly dependent upon levels of pre-irradiation. eloca correctly predicted the effect of small internal void volume of candu fuel elements in limiting sheath deformation. measured maximum sheath strains were up to a factor of 2.5 higher than calculations. as expected, fuel elements with beryllium brazed-on appendages deformed non-uniformly in the vicinity of the appendages. eloca, which is a uni-dimensional (radial) representation of a fuel element, was unable to model such non-uniform deformation. eloca correctly predicted the extent of potential failure mechanisms to candu fuel elements during a loca, such as localized sheath strains at tips of oxide (zro2) cracks and be beryllium braze assisted cracking of the sheath in the appendage regions. eloca also correctly predicted that none of the fuel elements would fail due to high stored energy deposited into the uo2 during the candu-pbf loca test nor due to excessive sheath strains prior to recrystallization of the zircaloy (athermal deformation). good agreement between data and calculations for other parameters (fuel centreline temperatures, etc.) was also found.
