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Pressurized Heavy Water Reactors

Pressurized Heavy Water Reactors
  • Author : Anonim
  • Publsiher : Elsevier
  • Release : 02 October 2021
  • ISBN : 0128232595
  • Pages : 542 pages
  • Rating : 4/5 from 21 ratings
GET THIS BOOKPressurized Heavy Water Reactors

Summary:
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 : Anonim
  • Publisher : Elsevier
  • Release : 02 October 2021
GET THIS BOOKPressurized Heavy Water Reactors

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

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Pressurized Heavy Water Reactors

Pressurized Heavy Water Reactors
  • Author : Jovica Riznic
  • Publisher : Elsevier
  • Release : 02 October 2021
GET THIS BOOKPressurized Heavy Water Reactors

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

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Dynamics and Control of Nuclear Reactors

Dynamics and Control of Nuclear Reactors
  • Author : Thomas W. Kerlin,Belle R. Upadhyaya
  • Publisher : Academic Press
  • Release : 05 October 2019
GET THIS BOOKDynamics and Control of Nuclear Reactors

Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on

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Nuclear Corrosion Science and Engineering

Nuclear Corrosion Science and Engineering
  • Author : Damien FERON
  • Publisher : Elsevier
  • Release : 21 February 2012
GET THIS BOOKNuclear Corrosion Science and Engineering

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

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Nuclear Safety in Light Water Reactors

Nuclear Safety in Light Water Reactors
  • Author : Bal Raj Sehgal
  • Publisher : Academic Press
  • Release : 19 May 2022
GET THIS BOOKNuclear Safety in Light Water Reactors

This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of

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An International Spent Nuclear Fuel Storage Facility

An International Spent Nuclear Fuel Storage Facility
  • Author : Russian Academy of Sciences,National Research Council,Policy and Global Affairs,Development, Security, and Cooperation,Office for Central Europe and Eurasia,Committee on the Scientific Aspects of an International Spent Nuclear Fuel Storage Facility in Russia
  • Publisher : National Academies Press
  • Release : 03 October 2005
GET THIS BOOKAn International Spent Nuclear Fuel Storage Facility

As part of a long-standing collaboration on nuclear nonproliferation, the National Academy of Sciences and the Russian Academy of Sciences held a joint workshop in Moscow in 2003 on the scientific aspects of an international radioactive disposal site in Russia. The passage of Russian laws permitting the importation and storage of high-level radioactive material (primarily spent nuclear fuel from reactors) has engendered interest from a number of foreign governments, including the U.S., in exploring the possibility of transferring material to

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Nuclear Energy Materials And Reactors - Volume I

Nuclear Energy Materials And Reactors - Volume I
  • Author : Yassin A. Hassan,Robin A. Chaplin
  • Publisher : EOLSS Publications
  • Release : 22 September 2010
GET THIS BOOKNuclear Energy Materials And Reactors - Volume I

Nuclear Energy Materials and Reactors is a component of Encyclopedia of Energy Sciences, Engineering and Technology Resources in the global Encyclopedia of Life Support Systems (EOLSS), which is an integrated compendium of twenty one Encyclopedias. Nuclear energy is a type of technology involving the controlled use of nuclear fission to release energy for work including propulsion, heat, and the generation of electricity. The theme on Nuclear Energy Materials and Reactors discusses: Fundamentals of Nuclear Energy; Nuclear Physics; Nuclear Interactions; Nuclear

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Understanding and Mitigating Ageing in Nuclear Power Plants

Understanding and Mitigating Ageing in Nuclear Power Plants
  • Author : Philip G Tipping
  • Publisher : Elsevier
  • Release : 26 October 2010
GET THIS BOOKUnderstanding and Mitigating Ageing in Nuclear Power Plants

Plant life management (PLiM) is a methodology focussed on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and licence renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the technical and economic requirements for safe, long-term operation. Understanding and mitigating ageing in nuclear power plants critically reviews the fundamental ageing-degradation

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Generic Safety Issues for Nuclear Power Plants with Pressurized Heavy Water Reactors and Measures for Their Resolution

This report covers generic safety issues (GSIs) thought to be of significance to Member States, based on a consensus process. The GSIs for pressurized heavy water reactors (PHWRs) compiled in this report reflect the broad experience of Member States in resolving safety concerns and in maintaining improvements to current practice. As can be seen from the actions taken in Member States with respect to the appropriate technical solutions, most issues have been successfully addressed. Those issues that have been generally

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Licensing Assessment of the Candu Pressurized Heavy Water Reactor. Preliminary Safety Information Document. Volume II. [USA].

ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (

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Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors

Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors
  • Author : International Atomic Energy Agency
  • Publisher : IAEA
  • Release : 19 May 2022
GET THIS BOOKAccident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors

This report contains practical guidance for performing accident analysis for nuclear power plants with pressurised heavy water reactors, based on current international good practice. It covers key aspects required including selection of initiating events and acceptance criteria, computer codes and modelling assumptions, the preparation of input data, presentation of results and quality assurance.

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Coolant Chemistry Control and Effects on Fuel Reliability in Pressurized Heavy Water Reactors

Coolant Chemistry Control and Effects on Fuel Reliability in Pressurized Heavy Water Reactors
  • Author : International Atomic Energy Agency
  • Publisher : Anonim
  • Release : 31 March 2021
GET THIS BOOKCoolant Chemistry Control and Effects on Fuel Reliability in Pressurized Heavy Water Reactors

Providing useful information on optimized chemistry control for pressurized heavy water reactors (PHWRs), this publication presents up to date knowledge on the topic including corrosion phenomena observed in the primary heat transport system and consequent effects on fuel reliability in PHWRs. Specifically, it describes the national practices on coolant chemistry control under various operating conditions and research and development programmes aiming to understand the corrosion phenomena (formation and transport) and related chemistry control. Crud deposit on the fuel cladding, the

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Nuclear Energy

Nuclear Energy
  • Author : Charles D. Ferguson
  • Publisher : Oxford University Press
  • Release : 17 May 2011
GET THIS BOOKNuclear Energy

Originally perceived as a cheap and plentiful source of power, the commercial use of nuclear energy has been controversial for decades. Worries about the dangers that nuclear plants and their radioactive waste posed to nearby communities grew over time, and plant construction in the United States virtually died after the early 1980s. The 1986 disaster at Chernobyl only reinforced nuclear power's negative image. Yet in the decade prior to the Japanese nuclear crisis of 2011, sentiment about nuclear power underwent a marked

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Generic Safety Issues for Nuclear Power Plants with Pressurized Heavy Water Reactors and Measures for Their Resolution

This report covers generic safety issues for pressurised heavy water reactors (PHWRs) which reflect the broad experience of Member States in resolving safety concerns and in maintaining improvements to current practice, with information useful in identifying areas, especially for enhanced designs of PHWRs, where safety upgrades should be considered. Those issues that have been generally resolved or concluded to be of low safety significance have not been included in the compilation.

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Handbook of Generation IV Nuclear Reactors

Handbook of Generation IV Nuclear Reactors
  • Author : Igor Pioro
  • Publisher : Woodhead Publishing
  • Release : 09 June 2016
GET THIS BOOKHandbook of Generation IV Nuclear Reactors

Handbook of Generation IV Nuclear Reactors presents information on the current fleet of Nuclear Power Plants (NPPs) with water-cooled reactors (Generation III and III+) (96% of 430 power reactors in the world) that have relatively low thermal efficiencies (within the range of 32 36%) compared to those of modern advanced thermal power plants (combined cycle gas-fired power plants – up to 62% and supercritical pressure coal-fired power plants – up to 55%). Moreover, thermal efficiency of the current fleet of NPPs with water-cooled reactors cannot be increased significantly

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