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Book Advanced Pressurized Water Reactor Study

Download or read book Advanced Pressurized Water Reactor Study written by U.S. Atomic Energy Commission. Division of Reactor Development and published by . This book was released on 1959 with total page 510 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Advanced Pressurized Water Reactor Study

Download or read book Advanced Pressurized Water Reactor Study written by Stone and Webster Engineering Corporation and published by . This book was released on 1960 with total page 262 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Advanced Pressurized Water Reactor Study

Download or read book Advanced Pressurized Water Reactor Study written by U.S. Atomic Energy Commission. Division of Reactor Development and published by . This book was released on 1959 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Advanced Pressurized Water Reactor Study

Download or read book Advanced Pressurized Water Reactor Study written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Study of Cost Effective Large Advanced Pressurized Water Reactors that Employ Passive Safety Features

Download or read book Study of Cost Effective Large Advanced Pressurized Water Reactors that Employ Passive Safety Features written by Y. Hayashi and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: A report of DOE sponsored portions of AP1000 Design Certification effort. On December 16, 1999, The United States Nuclear Regulatory Commission issued Design Certification of the AP600 standard nuclear reactor design. This culminated an 8-year review of the AP600 design, safety analysis and probabilistic risk assessment. The AP600 is a 600 MWe reactor that utilizes passive safety features that, once actuated, depend only on natural forces such as gravity and natural circulation to perform all required safety functions. These passive safety systems result in increased plant safety and have also significantly simplified plant systems and equipment, resulting in simplified plant operation and maintenance. The AP600 meets NRC deterministic safety criteria and probabilistic risk criteria with large margins. A summary comparison of key passive safety system design features is provided in Table 1. These key features are discussed due to their importance in affecting the key thermal-hydraulic phenomenon exhibited by the passive safety systems in critical areas. The scope of some of the design changes to the AP600 is described. These changes are the ones that are important in evaluating the passive plant design features embodied in the certified AP600 standard plant design. These design changes are incorporated into the AP1000 standard plant design that Westinghouse is certifying under 10 CFR Part 52. In conclusion, this report describes the results of the representative design certification activities that were partially supported by the Nuclear Energy Research Initiative. These activities are unique to AP1000, but are representative of research activities that must be driven to conclusion to realize successful licensing of the next generation of nuclear power plants in the United States.

Book Advanced Pressurized Water Reactor Study     Prepared by Stone   Webster Engineering Corporation and Combustion Engineering  Inc  for Division of Reactor Development  U S  Atomic Energy Commission  Etc

Download or read book Advanced Pressurized Water Reactor Study Prepared by Stone Webster Engineering Corporation and Combustion Engineering Inc for Division of Reactor Development U S Atomic Energy Commission Etc written by U.S. Atomic Energy Commission. Division of Reactor Development and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Advanced Pressurized Water Reactor for Improved Resource Utilization

Download or read book Advanced Pressurized Water Reactor for Improved Resource Utilization written by and published by . This book was released on 1981 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document is an interim report under ACDA BOA AC9NX707, Task Order 80-03, which covers the evaluation of certain potential improvements in pressurized water reactor designs intended to enhance uranium fuel utilization. The objective of these evaluations is to seek advanced, non-retrofittable improvements that could possibly be commercialized by the end of the century, and, on the basis of a preliminary evaluation, to select compatible improvements for incorporation into a composite advanced pressurized water reactor concept. The principal areas of investigation include reduced parasitic absorption of neutrons (Task 1), reduced neutron leakage (Task 2), and alternative fuel design concepts (Task 3). To the extent possible, the advanced concept developed in an earlier study (Retrofittable Modifications to Pressurized Water Reactors for Improved Resource Utilization, SSA-128, October 1980) is used as a basis in developing the advanced composite concept. The reference design considered typical of present PWR commercial practice is the system described in RESAR-414, Reference Safety Analysis Report, Westinghouse Nuclear Energy Systems, October 1976.

Book Accident Analysis for Nuclear Power Plants

Download or read book Accident Analysis for Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 2002 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: Accident analysis is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). The purpose of the report is to provide the necessary practical guidance for performing adequate accident analysis in the light of current good practice worldwide.

Book Advanced Reactor Development Program

Download or read book Advanced Reactor Development Program written by United States. Congress. Senate. Committee on Energy and Natural Resources. Subcommittee on Energy Research and Development and published by . This book was released on 1988 with total page 280 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Effects of Changing Economic Conditions on Fuel Cycle Costs in Pressurized Water Reactors

Download or read book The Effects of Changing Economic Conditions on Fuel Cycle Costs in Pressurized Water Reactors written by Manson Benedict and published by . This book was released on 1963 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study made by MIT for ECNG of the effect of changing economic conditions on fuel cycle costs in nuclear power systems is described. Fuel cycle costs are computed for eight different cost bases, which may be used to represent the effect of most of the combinations of economic condi tions likely to occur during the life of the reactor selected for study. This is an advanced pressurized-water reactor with free-standing stainless steel of Zircaloy fuel cladding, designed for a net electric output of 461 Mw. (Author).

Book Regulatory Policy for Advanced Nuclear Reactors

Download or read book Regulatory Policy for Advanced Nuclear Reactors written by United States. Congress. House. Committee on Science and Technology. Subcommittee on Energy Research and Production and published by . This book was released on 1986 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Pressurized Water Reactors

Download or read book Pressurized Water Reactors written by Yurugi Kanzaki and published by Elsevier. This book was released on 2024-07-26 with total page 507 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then guided through optimum design processes for PWRs, considering safety throughout. The authors then discuss thermal-hydraulic aspects within the PWR system and inside the reactor core, making this a valuable resource for nuclear and thermal engineers and researchers. Combining their wealth of experience, the book presents in-depth knowledge on the advancement and improvement of fuel rods that is gleaned from decades of experience and lessons learned. The inclusion of analysis codes for the design and safety elements ensure makes this a unique reference which will provide the reader with a solid understanding which they can transfer to their own professional and research settings. Future prospects for next generation PWR and Small Modular Reactors are also discussed, giving the reader a basis for further research of their own. Contains contributions from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes analysis codes, such as RELAP5, for the design and safety improvement of pressurized water reactors (PWRs) Presents history, examples, and case studies from Japan and other key regions, such as the United States and Europe

Book Nuclear Power

    Book Details:
  • Author : National Research Council
  • Publisher : National Academies Press
  • Release : 1992-02-01
  • ISBN : 0309043956
  • Pages : 234 pages

Download or read book Nuclear Power written by National Research Council and published by National Academies Press. This book was released on 1992-02-01 with total page 234 pages. Available in PDF, EPUB and Kindle. Book excerpt: The construction of nuclear power plants in the United States is stopping, as regulators, reactor manufacturers, and operators sort out a host of technical and institutional problems. This volume summarizes the status of nuclear power, analyzes the obstacles to resumption of construction of nuclear plants, and describes and evaluates the technological alternatives for safer, more economical reactors. Topics covered include: Institutional issues-including regulatory practices at the federal and state levels, the growing trends toward greater competition in the generation of electricity, and nuclear and nonnuclear generation options. Critical evaluation of advanced reactors-covering attributes such as cost, construction time, safety, development status, and fuel cycles. Finally, three alternative federal research and development programs are presented.

Book Advanced Reactor Concepts  ARC

Download or read book Advanced Reactor Concepts ARC written by Ali Zamani Paydar and published by Elsevier. This book was released on 2023-07-20 with total page 454 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear engineers advancing the energy transition are understanding more about the next generation of nuclear plants; however, it is still difficult to access all the critical types, concepts, and applications in one location. Advanced Reactor Concepts (ARC): A New Nuclear Power Plant Perspective Producing Energy gives engineers and nuclear engineering researchers the comprehensive tools to get up to date on the latest technology supporting generation IV nuclear plant systems. After providing a brief history of this area, alternative technology is discussed such as electromagnetic pumps, heat pipes as control devices, Nuclear Air-Brayton Combined Cycles integration, and instrumentation helping nuclear plants to provide dispatchable electricity to the grid and heat to industry. Packed with examples of all the types, benefits, and challenges involved, Advanced Reactor Concepts (ARC) delivers the go-to reference that engineers need to advance safe nuclear energy as a low-carbon option. Describes theory and concepts on generation IV technology such as advanced reactor concepts (ARC) and electromagnetic pumps, and compares different types and sizes. Sets out the energy transition with critical carbon-free technology that can supplement intermittent power sources such as wind and solar. Explains alternative heat storage technology, including Nuclear Air-Brayton Combined Cycles. Introduces advanced main instrumentation systems for in-core probes.