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Nuclear Power Reactor Designs

Nuclear Power Reactor Designs PDF Author: Jun Wang
Publisher: Elsevier
ISBN: 0323999468
Category : Science
Languages : en
Pages : 465

Book Description
Nuclear Power Reactor Designs: From History to Advances analyzes nuclear designs throughout history and explains how each of those has helped to shape and inform the nuclear reactor designs of today and the future. Focused on the structure, systems and relevant components of each reactor design, this book provides the readers with answers to key questions to help them understand the benefits of each design. Each reactor design is introduced, their origin defined, and the relevant research presented before an analysis of its successes, what was learned, and how research and technology advanced as a result are presented. Students, researchers and early career engineers will gain a solid understanding of how nuclear designs have evolved, and how they will continue to develop in the future. - Presents reactor designs through history to present day, focusing on key structures, systems and components - Provides readers with quick answers about various design principles and rationales - Includes new approaches such as the micro-reactor and small-modular reactors

Nuclear Power Reactor Designs

Nuclear Power Reactor Designs PDF Author: Jun Wang
Publisher: Elsevier
ISBN: 0323999468
Category : Science
Languages : en
Pages : 465

Book Description
Nuclear Power Reactor Designs: From History to Advances analyzes nuclear designs throughout history and explains how each of those has helped to shape and inform the nuclear reactor designs of today and the future. Focused on the structure, systems and relevant components of each reactor design, this book provides the readers with answers to key questions to help them understand the benefits of each design. Each reactor design is introduced, their origin defined, and the relevant research presented before an analysis of its successes, what was learned, and how research and technology advanced as a result are presented. Students, researchers and early career engineers will gain a solid understanding of how nuclear designs have evolved, and how they will continue to develop in the future. - Presents reactor designs through history to present day, focusing on key structures, systems and components - Provides readers with quick answers about various design principles and rationales - Includes new approaches such as the micro-reactor and small-modular reactors

Nuclear Reactor Analysis

Nuclear Reactor Analysis PDF Author: James J. Duderstadt
Publisher: Wiley
ISBN: 9780471223634
Category : Technology & Engineering
Languages : en
Pages : 0

Book Description
Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores. This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural. The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermal-hydraulics or materials studies, which play a major role in determining a reactor design.

Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3

Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3 PDF Author: Chengmin Liu
Publisher: Springer Nature
ISBN: 9811988994
Category : Science
Languages : en
Pages : 1260

Book Description
This is the third in a series of three volumes of proceedings of the 23rd Pacific Basin Nuclear Conference (PBNC 2022) which was held by Chinese Nuclear Society. As one in the most important and influential conference series of nuclear science and technology, the 23rd PBNC was held in Beijing and Chengdu, China in 2022 with the theme “Nuclear Innovation for Zero-carbon Future”. For taking solid steps toward the goals of achieving peak carbon emissions and carbon neutrality, future-oriented nuclear energy should be developed in an innovative way for meeting global energy demands and coordinating the deployment mechanism. It brought together outstanding nuclear scientists and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The proceedings highlight the latest scientific, technological and industrial advances in Nuclear Safety and Security, Operations and Maintenance, New Builds, Waste Management, Spent Fuel, Decommissioning, Supply Capability and Quality Management, Fuel Cycles, Digital Reactor and New Technology, Innovative Reactors and New Applications, Irradiation Effects, Public Acceptance and Education, Economics, Medical and Biological Applications, and also the student program that intends to raise students’ awareness in fully engaging in this career and keep them updated on the current situation and future trends. These proceedings are not only a good summary of the new developments nuclear science and technology, but also a useful guideline for the researchers, engineers and graduate students.

Reactor Fuels, Materials and Systems under Extreme Environments

Reactor Fuels, Materials and Systems under Extreme Environments PDF Author: Wenzhong Zhou
Publisher: Frontiers Media SA
ISBN: 2889747662
Category : Technology & Engineering
Languages : en
Pages : 360

Book Description


Nuclear Fuel Safety Criteria

Nuclear Fuel Safety Criteria PDF Author: OECD Nuclear Energy Agency
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 74

Book Description
Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.

The Linear Reactivity Model for Nuclear Fuel Management

The Linear Reactivity Model for Nuclear Fuel Management PDF Author: M. J. Driscoll
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 270

Book Description
The Linear Reactivity Model (LRM) is a simple nuclear fuel management model that comes with a diskette containing three programs. Consisting of a collection of algorithms and methods, the LRM describes complex core behavior, but it is simpler than the complex programs developed for design calculations. This makes the LRM particularly useful as a teaching tool to explain the basic principles of nuclear fuel management. The LRM mainly focuses on the pressurized water reactor, but it is also directly applicable to the boiling water reactor. Application of the LRM to the CANDU reactor is also covered.

Simulation Using the Monte Carlo Method

Simulation Using the Monte Carlo Method PDF Author: Rocco F. Iuorno
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72

Book Description


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

Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201080202
Category :
Languages : en
Pages : 218

Book Description
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.

Structural Materials for Generation IV Nuclear Reactors

Structural Materials for Generation IV Nuclear Reactors PDF Author: Pascal Yvon
Publisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686

Book Description
Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area

Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors

Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 416

Book Description
The thermophysical properties database for materials of light water reactors and heavy water reactors described in this technical document was established within the framework of an IAEA Coordinated Research Project. The database is intended to serve as a useful source of information on thermophysical properties data for water cooled reactor analyses. In particular, it aims at achieving improvements in safety and economics of future plants by helping to remove the need for large design margins to account for limitations of data and methods. The database has been developed into an internationally available Internet database (THERPRO) at Hanyang University (Republic of Korea), and now provides various materials properties data and an interactively accessible information resource and communications medium for researchers and engineers.--Publisher's description.