Improving the Calandria Tubes for CANDU Reactors [electronic Resource] PDF Download
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Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ontario : Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages :
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![Improving the Calandria Tubes for CANDU Reactors [electronic Resource] PDF](https://books.google.com/books/content/images/frontcover/zrHXxgEACAAJ?fife=w80-h100)
Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ontario : Chalk River Laboratories
ISBN:
Category :
Languages : en
Pages :
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Author: C. E. Coleman
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Recent inspections have indicated that carbon steel outlet feeder pipes in some candu reactors are experiencing wall loss near the exit from the reactor core. this phenomenon is not observed in inlet feeder pipes. examination of a sample of pipe removed from a candu 6 reactor has indicated that the mechanism causing the wall loss is flow-accelerated corrosion (fac), at rates higher than expected, but two orders of magnitude lower than those typically observed in secondary circuits of nuclear and conventional power plants. although the candu reactor outlet feeder operating temperatures and the use of lioh at a high ph should have ensured low corrosion rates, use of sa 106 grade b carbon steel with a low chromium content resulted in some susceptibility to fac. the main parameter influencing the rate of wall loss is the coolant velocity, with the bend angle playing a secondary role. a solubility-based mathematical model describing the effects of water chemistry and coolant hydrodynamics on the rate of fac has been developed and has been recently improved by the empirical incorporation of the effect of electrochemical potential on the solubility of magnetite. experiment and theory have indicated that the corrosion rates are lower at lower ph values within the permissible operating range. experiments are being conducted to obtain more information on the effects of water chemistry and material composition on fac. current results support the predicted effects of ph and carbon steel chromium content on the fac rate. remedial measures implemented include operation of existing reactors at the lower end of the specified ph range and the specification of a minimum of 0.20 wt% cr in the carbon steel of feeder pipes of future candu reactors.
Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
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Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Author: B. A. Cheadle
Publisher: Chalk River, Ont. : Reactor Materials Division, Chalk River Laboratories
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 56
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Author: A. M. Garde
Publisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805
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Book Description
Author: Damien Feron
Publisher: Elsevier
ISBN: 085709534X
Category : Technology & Engineering
Languages : en
Pages : 1073
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Book Description
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
Author: A.K. Suri
Publisher: Routledge
ISBN: 135144896X
Category : Science
Languages : en
Pages : 278
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Book Description
The growth and development witnessed today in modern science, engineering, and technology owes a heavy debt to the rare, refractory, and reactive metals group, of which niobium is a member. Extractive Metallurgy of Niobium presents a vivid account of the metal through its comprehensive discussions of properties and applications, resources and resource processing, chemical processing and compound preparation, metal extraction, and refining and consolidation. Typical flow sheets adopted in some leading niobium-producing countries for the beneficiation of various niobium sources are presented, and various chemical processes for producing pure forms of niobium intermediates such as chloride, fluoride, and oxide are discussed. The book also explains how to liberate the metal from its intermediates and describes the physico-chemical principles involved. It is an excellent reference for chemical metallurgists, hydrometallurgists, extraction and process metallurgists, and minerals processors. It is also valuable to a wide variety of scientists, engineers, technologists, and students interested in the topic.
Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1680
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Author:
Publisher: Elsevier
ISBN: 0128220546
Category : Science
Languages : en
Pages : 544
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Book Description
Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs. Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties. Provides a complete reference dedicated to the latest research on Pressurized Heavy Water Reactors and their economic and environmental benefits Goes beyond CANDU reactors to analyze the popular German and Indian designs, as well as plant design in Korea, Romania, China and Argentina Spans all phases of the nuclear power plant lifecycle, from design, manufacturing, operation, maintenance and long-term operation
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 782
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