Worldwide Assessment of Steam-generator Problems in Pressurized-water-reactor Nuclear Power Plants

Worldwide Assessment of Steam-generator Problems in Pressurized-water-reactor Nuclear Power Plants
Author:
Publisher:
Total Pages:
Release: 1981
Genre:
ISBN:

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Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

Steam Generators for Nuclear Power Plants

Steam Generators for Nuclear Power Plants
Author: Jovica Riznic
Publisher: Woodhead Publishing
Total Pages: 580
Release: 2017-05-24
Genre: Technology & Engineering
ISBN: 0081009283

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Steam Generators for Nuclear Power Plants examines all phases of the lifecycle of nuclear steam generators (NSGs), components which are essential for the efficient and safe operation of light water reactors (LWRs). Coverage spans the design, manufacturing, operation and maintenance, fitness-for-service, and long-term operation of these key reactor parts. Part One opens with a chapter that provides fundamental background on NSG engineering and operational experiences. Following chapters review the different NSG concepts, describe NSG design and manufacturing, and consider the particularities of SGs for VVER reactors. Part Two focuses on NSG operation and maintenance, starting with an overview of the activities required to support reliable and safe operation. The discussion then moves on to tubing vibration, followed by the water and steam cycle chemistry issues relevant to the NSG lifecycle. Finally, a number of chapters focus on the key issue of corrosion in NSGs from different angles. This book serves as a timely resource for professionals involved in all phases of the NSG lifecycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long-term operation. It is also intended as a valuable resource for students and researchers interested in a range of topics relating to NSG lifecycle management. Fulfills the need for a detailed reference on steam generators for nuclear power plants Contains comprehensive coverage of all phases of the nuclear steam generator lifecycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long-term operation in one convenient volume Presents contributions from key manufacturers and research institutes and universities

Pressurized Heavy Water Reactors

Pressurized Heavy Water Reactors
Author:
Publisher: Elsevier
Total Pages: 546
Release: 2021-10-02
Genre: Science
ISBN: 0128232595

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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

Pressurized Heavy Water Reactors

Pressurized Heavy Water Reactors
Author: Jovica Riznic
Publisher: Elsevier
Total Pages: 587
Release: 2021-10-02
Genre: Business & Economics
ISBN: 0323853838

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Pressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components, and the role of codes in PHWR and Nuclear Regulation and Licensing. Including contemporary capabilities and challenges of nuclear technology, the book offers solutions and advice on common problems faced, guiding the reader through safe and approved processes that will help them reach suitable solutions. Professionals involved in lifecycle assessments and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing. A comprehensive reference on the latest research on Atucha Pressurized Heavy Water Reactors and their impact on sustainability goals Analyzes The Atucha-2 BEPU and LBLOCA Considers the licensing of Atucha-2, its physics and aging management of major components

Physical and Statistical Models for Steam Generator Clogging Diagnosis

Physical and Statistical Models for Steam Generator Clogging Diagnosis
Author: Sylvain Girard
Publisher: Springer
Total Pages: 102
Release: 2014-07-26
Genre: Technology & Engineering
ISBN: 3319093215

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Clogging of steam generators in nuclear power plants is a highly sensitive issue in terms of performance and safety and this book proposes a completely novel methodology for diagnosing this phenomenon. It demonstrates real-life industrial applications of this approach to French steam generators and applies the approach to operational data gathered from French nuclear power plants. The book presents a detailed review of in situ diagnosis techniques and assesses existing methodologies for clogging diagnosis, whilst examining their limitations. It also addresses numerical modelling of the dynamic behaviour of steam generators and provides a thorough analysis of statistical methods for sensitivity analysis and dimension reduction. Steam generators are heat exchangers found in nuclear power plants and over time they become increasingly clogged by iron oxides. This clogging then hampers the flow inside steam generators and compromises their mechanical integrity, which hinders performance and safety. This book is intended for nuclear safety specialists, nuclear performance engineers and researchers and postgraduate students working on heat exchanger modeling and computational engineering.

Operation and Performance Analysis of Steam Generators in Nuclear Power Plants

Operation and Performance Analysis of Steam Generators in Nuclear Power Plants
Author: Siniša Šadek
Publisher:
Total Pages:
Release: 2017
Genre: Technology
ISBN:

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Steam generators are components in which heat produced in the reactor core is transferred to the secondary side, the steam supply system, of the nuclear power plant (NPP). Steam generators (SGs) have to fulfil special nuclear regulatory requirements regarding their size, selection of materials, pressure loads, impact on the NPP safety, et cetera The primary-side fluid is liquid water at the high pressure, and the fluid on the secondary side is saturated water-steam mixture at the pressure twice as low. A special attention is given to preserving the boundary between the contaminated water in the primary reactor coolant system and the water-steam mixture in the secondary system. A brief overview of the SG design, its operation and the mathematical correlations used to quantify heat transfer is given in the chapter. Results of the SG transient behaviour obtained by the simulation with the best-estimate computer code RELAP5, developed for safety analyses of NPPs, are also presented. Two types of steam generators are analyzed: the inverted U-tube SG, which is commonly found in the present-day pressurized water reactors and the helical-coil SG that is part of the new-generation reactor designs.

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety
Author: International Atomic Energy Agency
Publisher: IAEA
Total Pages: 128
Release: 2005
Genre: Business & Economics
ISBN:

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The objective of this report is to identify significant ageing mechanisms and degradation locations, as well as to document current practices for the assessment and management of the ageing of boiling water reactor (BWR) pressure vessel internals (RPVIs). The report emphasizes safety aspects and also provides information on current inspections as well as on monitoring and mitigation practices for managing ageing of BWR RPVs.

International Standard Problem No. 20

International Standard Problem No. 20
Author: OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations
Publisher:
Total Pages: 76
Release: 1988
Genre:
ISBN:

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