Input Output Manual Of Light Water Reactor Fuel Analysis Code Femaxi 7 And Its Related Codes
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Author | : Yoshiaki Oka |
Publisher | : Springer Science & Business Media |
Total Pages | : 664 |
Release | : 2010-07-01 |
Genre | : Technology & Engineering |
ISBN | : 1441960341 |
Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.
Author | : |
Publisher | : |
Total Pages | : 1130 |
Release | : 1985 |
Genre | : Government publications |
ISBN | : |
Author | : John Gittus |
Publisher | : |
Total Pages | : 736 |
Release | : 1983 |
Genre | : Technology & Engineering |
ISBN | : |
Author | : Dan Gabriel Cacuci |
Publisher | : Springer Science & Business Media |
Total Pages | : 3701 |
Release | : 2010-09-14 |
Genre | : Science |
ISBN | : 0387981306 |
This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.
Author | : Jun Wang |
Publisher | : Woodhead Publishing |
Total Pages | : 612 |
Release | : 2020-11-10 |
Genre | : Technology & Engineering |
ISBN | : 0128181915 |
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. - Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors - Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes - Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
Author | : International Atomic Energy Agency |
Publisher | : |
Total Pages | : 180 |
Release | : 2020-02-29 |
Genre | : Technology & Engineering |
ISBN | : 9789201639196 |
This publication summarizes the findings and conclusions of an IAEA coordinated research project (CRP) on fuel modelling in accident conditions, which was initiated under the IAEA Action Plan on Nuclear Safety following the Fukushima accident. The overall aim of the project was to analyse and better understand fuel behavior in accident conditions, with a focus on loss of coolant accidents. In the course of the project the participants used a mixture of data derived from accident simulation experiments, in particular data designed to investigate the fuel behaviour during design basis accident and design extension conditions. They carried out calculations on priority cases selected from a matrix of cases identified at the first research coordination meeting and designed to support their individual priorities. These priority cases were chosen as the best available to help determine which of the many models used in the codes best reflect reality. The CRP provided an ideal platform to compare their code results with others and especially with experimental data, to which they otherwise would not have had access. The achievements made within this CRP fostered new collaborations and enhanced the development and improvement of common models and highlighted differences in the interpretation of some experiments and therefore in the use of the codes ? the so-called user effects.
Author | : NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour |
Publisher | : OECD |
Total Pages | : 96 |
Release | : 1995 |
Genre | : Technology & Engineering |
ISBN | : |
Author | : Yoshiaki Oka |
Publisher | : Springer |
Total Pages | : 337 |
Release | : 2014-06-11 |
Genre | : Technology & Engineering |
ISBN | : 443154898X |
This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.
Author | : International Atomic Energy Agency |
Publisher | : IAEA Tecdoc |
Total Pages | : 0 |
Release | : 2015 |
Genre | : Science |
ISBN | : 9789201053152 |
One of the greatest challenges for nuclear energy is how to properly manage the highly radioactive waste generated during irradiation in nuclear reactors. Accelerator Driven Systems (ADSs) may offer new prospects and advantages for the transmutation of such high level nuclear waste. ADS or accelerator driven transmutation of waste (ATW) consists of a high power proton accelerator, a heavy metal spallation target that produces neutrons when bombarded by the high power beam, and a sub-critical core that is neutronically coupled to the spallation target. This publication provides a comprehensive state of the art of the ADS technology by representing the different ADS concepts proposed worldwide in the last 15 years, as well as the related R&D activities and demonstration initiatives carried out at national international level.
Author | : Kazys Almenas |
Publisher | : |
Total Pages | : 198 |
Release | : 1998 |
Genre | : Nuclear power plants |
ISBN | : 9789986492351 |