Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes

Author: Jun Wang

Publisher: Woodhead Publishing

Published: 2020-11-10

Total Pages: 612

ISBN-13: 0128181915

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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


Neutronic Analysis For Nuclear Reactor Systems

Neutronic Analysis For Nuclear Reactor Systems

Author: Bahman Zohuri

Publisher: Springer

Published: 2016-11-01

Total Pages: 560

ISBN-13: 3319429647

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This book covers the entire spectrum of the science and technology of nuclear reactor systems, from underlying physics, to next generation system applications and beyond. Beginning with neutron physics background and modeling of transport and diffusion, this self-contained learning tool progresses step-by-step to discussions of reactor kinetics, dynamics, and stability that will be invaluable to anyone with a college-level mathematics background wishing to develop an understanding of nuclear power. From fuels and reactions to full systems and plants, the author provides a clear picture of how nuclear energy works, how it can be optimized for safety and efficiency, and why it is important to the future.


Thorium Fuel Cycle

Thorium Fuel Cycle

Author: International Atomic Energy Agency

Publisher:

Published: 2005

Total Pages: 120

ISBN-13:

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Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.


NUREG/CR.

NUREG/CR.

Author: U.S. Nuclear Regulatory Commission

Publisher:

Published: 1977

Total Pages: 16

ISBN-13:

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Author: Jyeshtharaj Joshi

Publisher: Woodhead Publishing

Published: 2019-06-09

Total Pages: 890

ISBN-13: 0081023383

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. - Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors - Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future - Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization


Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor

Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor

Author: Brian Boer

Publisher:

Published: 2008

Total Pages: 0

ISBN-13: 9781586039660

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The Very High Temperature Reactor (VHTR) has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. As one of the fourth generation nuclear reactors, the VHTR is characterized by high plant efficiency and a high fuel discharge burn-up level. More specifically, the (pebble-bed type) High Temperature Reactor (HTR) is known for its inherently safe characteristics, coming from a negative temperature reactivity feedback, a low power density and a large thermal inertia of the core.


Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Author: International Atomic Energy Agency

Publisher:

Published: 2012-06

Total Pages: 639

ISBN-13: 9789201253101

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This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.


Fundamentals of Nuclear Reactor Physics

Fundamentals of Nuclear Reactor Physics

Author: Elmer E. Lewis

Publisher: Elsevier

Published: 2008-01-18

Total Pages: 311

ISBN-13: 0080560431

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Fundamentals of Nuclear Reactor Physics offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation . It provides a clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release. It provides in-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution. It includes ample worked-out examples and over 100 end-of-chapter problems. Engineering students will find this applications-oriented approach, with many worked-out examples, more accessible and more meaningful as they aspire to become future nuclear engineers. - A clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release - In-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution - Ample worked-out examples and over 100 end-of-chapter problems - Full Solutions Manual


Numerical and Experimental Studies on Small/Micro Nuclear Reactors

Numerical and Experimental Studies on Small/Micro Nuclear Reactors

Author: Yugao Ma

Publisher: Frontiers Media SA

Published: 2024-04-01

Total Pages: 133

ISBN-13: 2832547036

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Future space missions and deep-sea explorations will require small/micro nuclear reactors (kWe~MWe) for power generation. Compared with conventional energy systems such as storage batteries and fossil energy, nuclear reactors are featured higher energy intensity, higher reliability, and longer lifetime. According to the coolant, the candidate small/micro nuclear reactors include the heat pipe cooled reactor, liquid metal cooled reactor, and gas-cooled reactor, most of which are still in the conceptual design stage with numerical studies and experimental research. These emerging reactors have an entirely different core structure and working principle from the existing light water reactors, which has led to an increasing need for updated simulation methods and experimental studies.


Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions

Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions

Author: International Atomic Energy Agency

Publisher:

Published: 2020-07-30

Total Pages: 218

ISBN-13: 9789201080202

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This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.