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An Accurate Model For Pressure Drop Prediction In Multi Element Candu Fuel Channels
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Book Synopsis An accurate model for pressure drop prediction in multi-element CANDU fuel channels by : C. W. Snoek
Download or read book An accurate model for pressure drop prediction in multi-element CANDU fuel channels written by C. W. Snoek and published by . This book was released on 1986 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: On august 10, 1974, heavy water from the heat transport system of pickering generating station reactor unit 3, was detected in the gas annulus system. it was quickly determined that a pressure tube was leaking and a decision was made to identify and replace the defective tube. during the ensuing days, the first leaking tube was actually located by a sectionalizing and freezing technique with some secondary help from an acoustic emission search. however, two other subsequent leaking tubes were located initially by the acoustic emission technique. this report outlines in chronological order the first acoustic emission leak detection attempt, the subsequent development of a reproducible leak detection technique and finally the use of acoustic emission as the primary method for identification of suspect leaking pressure tubes.
Book Synopsis A comparison of prediction methods for pressure drop in multi-element CANDU-fuel channels by : C. W. Snoek
Download or read book A comparison of prediction methods for pressure drop in multi-element CANDU-fuel channels written by C. W. Snoek and published by . This book was released on 1986 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A generalized prediction method for single-phase pressure drop in a string of aligned CANDU-type bundles by : L. K. H. Leung
Download or read book A generalized prediction method for single-phase pressure drop in a string of aligned CANDU-type bundles written by L. K. H. Leung and published by . This book was released on 2001 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The btf-105 experiment in the blowdown test facility is one of a series of experiments sponsored by the candu owners group (cog) to determine the release, transport and deposition of fission products from nuclear fuel under high-temperature transient conditions. the btf-105 experiment has been broken up into two tests: btf-105a and btf-105b. the btf-105a test is a precursor to the btf-105b test, which will generate fission product release data used to benchmark candu safety analysis codes. the btf-105a test will be used to assess instrumentation and procedures to be used during btf-105b, and to generate correlations between fuel sheath and fuel centreline temperatures. fission product release and transport data will also be obtained from low burnup fuel. the btf-105a test consists of a fuel stringer containing a single unirradiated instrumented zircaloy-clad uo2 fuel element. the assembly will be irradiated at a linear power of 50 kw/m for 10 days to establish an inventory of fission products in the fuel. following the soak irradiation, the stringer will be subjected to a coolant blowdown where the volume average temperature of the uo2 will rise to and be maintained at about 1600-1800 degrees c for about 10 minutes. the fuel element is predicted to fail during the ramp up to this temperature due to complete oxidation of the sheath. fission products released during the transient will be monitored by gamma spectrometers. following the test, the fuel stringer will be removed from the reactor and destructively examined in the crl hot cells. grab samples from inside the test section will also be removed and analyzed for fission products. this report presents an overall plan for the activities to be completed before, during and after the btf-105a blowdown test.
Book Synopsis Particulate Phenomena and Multiphase Transport by : T. Nejat Veziroğlu
Download or read book Particulate Phenomena and Multiphase Transport written by T. Nejat Veziroğlu and published by . This book was released on 1988 with total page 688 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fifth International Conference on Simulation Methods in Nuclear Engineering, September 8-11, 1996, Montreal, Canada by :
Download or read book Fifth International Conference on Simulation Methods in Nuclear Engineering, September 8-11, 1996, Montreal, Canada written by and published by . This book was released on 1996 with total page 524 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Interim analysis of pressure drop in CANDU fuel bundle designs by : G. D. Mcpherson
Download or read book Interim analysis of pressure drop in CANDU fuel bundle designs written by G. D. Mcpherson and published by . This book was released on 1960 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pressure drop measurements on bruce-type 37-element CANDU fuel bundles in freon phase-i aligned bundles by : A. Hameed
Download or read book Pressure drop measurements on bruce-type 37-element CANDU fuel bundles in freon phase-i aligned bundles written by A. Hameed and published by . This book was released on 1995 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Some aspects of frictional pressure drop in CANDU reactor fuel bundles by : G. M. Barns
Download or read book Some aspects of frictional pressure drop in CANDU reactor fuel bundles written by G. M. Barns and published by . This book was released on 1981 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pressure drops in a CANDU 600 mw fuel channel in water and steam water flow preliminary analysis by : C. F. Forrest
Download or read book Pressure drops in a CANDU 600 mw fuel channel in water and steam water flow preliminary analysis written by C. F. Forrest and published by . This book was released on 1978 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Hydraulic tests of c19c15a, c19c158 and c19x8d fuel bundles, and summary of predicted reactor core pressure drops for CANDU fuel bundle designs by : G. J. Clarke
Download or read book Hydraulic tests of c19c15a, c19c158 and c19x8d fuel bundles, and summary of predicted reactor core pressure drops for CANDU fuel bundle designs written by G. J. Clarke and published by . This book was released on 1960 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-11 with total page 486 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings, ... Annual Conference by : Canadian Nuclear Society. Conference
Download or read book Proceedings, ... Annual Conference written by Canadian Nuclear Society. Conference and published by . This book was released on 1986 with total page 342 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Fuel Cycle Science and Engineering by : Ian Crossland
Download or read book Nuclear Fuel Cycle Science and Engineering written by Ian Crossland and published by Elsevier. This book was released on 2012-09-21 with total page 649 pages. Available in PDF, EPUB and Kindle. Book excerpt: The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field. Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management. With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. Provides a comprehensive and holistic review of the complete nuclear fuel cycle Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication
Download or read book INIS Atomindex written by and published by . This book was released on 1995 with total page 682 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pressure Vessels and Piping Codes and Standards by :
Download or read book Pressure Vessels and Piping Codes and Standards written by and published by . This book was released on 1998 with total page 556 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :International Atomic Energy Agency Publisher :International Atomic Energy Agency ISBN 13 :9789201396105 Total Pages :169 pages Book Rating :4.3/5 (961 download)
Book Synopsis Benchmark Analyses on the Natural Circulation Test Performed During the Phenix End-Of-Life Experiments: IAEA Tecdoc Series by : International Atomic Energy Agency
Download or read book Benchmark Analyses on the Natural Circulation Test Performed During the Phenix End-Of-Life Experiments: IAEA Tecdoc Series written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2013-07-01 with total page 169 pages. Available in PDF, EPUB and Kindle. Book excerpt: "This publication is based on the experience of an IAEA coordinated research project on control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments. Presented in this publication are the benchmark analyses of the natural circulation test performed before the definite shutdown of the reactor. The experimental data gathered during these tests represent a unique resource to carry out validation analyses and code-to-code comparisons. The benchmark analyses allowed participants to investigate and verify several system and safety codes currently used in the analyses of liquid metal thermal hydraulics phenomena in sodium fast reactors."--Publisher's description.
Book Synopsis Nuclear Corrosion Science and Engineering by : Damien Feron
Download or read book Nuclear Corrosion Science and Engineering written by Damien Feron and published by Elsevier. This book was released on 2012-02-21 with total page 1073 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches
