Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants
Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants

Author: IAEA

Publisher:

Published: 2024-06

Total Pages: 0

ISBN-13: 9789204421231

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This Safety Guide provides recommendations on how to meet the requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) in relation to the reactor coolant system and associated systems for nuclear power plants. It is a revision of IAEA Safety Standards Series No. NS-G-1.9, which it supersedes. The publication takes into account developments, experience and practices in the design of nuclear power plants throughout their lifetime. It references and considers other IAEA safety standards that are relevant and related to the design of the reactor coolant system and associated systems for nuclear power plants. Recommendations to achieve the required reliability of the capabilities designed to transfer residual heat to the ultimate heat sink in the different plant states are also included. As those systems are dependent on specific reactor technologies, more appropriate recommendations have been developed respectively for pressurized light water reactors, boiling water reactors and pressurized heavy water reactors.

Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants
Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants

Author: IAEA

Publisher: International Atomic Energy Agency

Published: 2020-03-03

Total Pages: 117

ISBN-13: 9201064225

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This Safety Guide provides recommendations on how to meet the requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) in relation to the reactor coolant system and associated systems for nuclear power plants. It is a revision of IAEA Safety Standards Series No. NS-G-1.9, which it supersedes. The publication takes into account developments, experience and practices in the design of nuclear power plants throughout their lifetime. It references and considers other IAEA safety standards that are relevant and related to the design of the reactor coolant system and associated systems for nuclear power plants. Recommendations to achieve the required reliability of the capabilities designed to transfer residual heat to the ultimate heat sink in the different plant states are also included. As those systems are dependent on specific reactor technologies, more appropriate recommendations have been developed respectively for pressurized light water reactors, boiling water reactors and pressurized heavy water reactors.

Design of the Reactor Containment and Associated Systems for Nuclear Power Plants
Design of the Reactor Containment and Associated Systems for Nuclear Power Plants

Author: IAEA

Publisher: International Atomic Energy Agency

Published: 2019-12-09

Total Pages: 86

ISBN-13: 9201072228

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This Safety Guide provides recommendations on meeting the requirements of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) relevant to reactor containment and associated systems. The publication addresses the containment structure and the systems with the functions of isolation, control and management of mass and energy releases, control and limitation of radioactive releases, and control and management of combustible gases. The Safety Guide is intended for use primarily for land based, stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat generating applications, such as for district heating or desalination.

Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants
Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants

Author: International Atomic Energy Agency

Publisher: International Atomic Energy Agency

Published: 2020-05-30

Total Pages: 99

ISBN-13: 9789201057198

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This Safety Guide provides recommendations on how to meet the requirements established in IAEA Safety Standards Series No. SSR-2/1(Rev. 1) in relation to the reactor coolant system and associated systems for nuclear power plants. It is a revision of IAEA Safety Standards Series No. NS-G-1.9 which it supersedes. The publication takes into account developments, experience and practices in the design of nuclear power plants throughout their lifetime. It references and considers other IAEA safety standards that are relevant and related to the design of the reactor coolant system and associated systems for nuclear power plants. Recommendations to achieve the required reliability of the capabilities designed to transfer residual heat to the ultimate heat sink in the different plant states are also included. As those systems are dependent on specific reactor technologies, more appropriate recommendations have been developed for pressurized light water reactors, boiling water reactors and pressurized heavy water reactors respectively.

Reactor Coolant and Associated Systems in Nuclear Power Plants
Reactor Coolant and Associated Systems in Nuclear Power Plants

Author: International Atomic Energy Agency

Publisher:

Published: 1986

Total Pages: 96

ISBN-13:

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Covers the safety design considerations for various reactor coolant and associated systems for operational states and accident conditions including the selection, sizing and reliability aspects. This includes safety systems such as emergency core cooling, residual heat removal or emergency feedwater systems.

Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants
Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants

Author: International Atomic Energy Agency

Publisher:

Published: 2004

Total Pages: 790

ISBN-13:

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This publication is a revision and combination of two previous Safety Guides: Safety Series No. 50-SG-D6, Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1981), and Safety Series No. 50-SG-D13, Reactor Coolant and Associated Systems in Nuclear Power Plants (1986). The revision takes account of developments in the design of the reactor coolant and associated systems in nuclear power plants since the earlier Safety Guides were published. The other objectives of the revision are to ensure consistency with the Requirements for Design, issued in 2000, and.

Safety of Nuclear Power Plants
Safety of Nuclear Power Plants

Author: International Atomic Energy Agency

Publisher:

Published: 2012

Total Pages: 0

ISBN-13: 9789201215109

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On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Nuclear Power Safety
Nuclear Power Safety

Author: James H. Rust

Publisher: Elsevier

Published: 2013-10-22

Total Pages: 419

ISBN-13: 1483285448

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A concise and current treatment of the subject of nuclear power safety, this work addresses itself to such issues of public concern as: radioactivity in routine effluents and its effect on human health and the environment, serious reactor accidents and their consequences, transportation accidents involving radioactive waste, the disposal of radioactive waste, particularly high-level wastes, and the possible theft of special nuclear materials and their fabrication into a weapon by terrorists. The implementation of the defense-in-depth concept of nuclear power safety is also discussed. Of interest to all undergraduate and graduate students of nuclear engineering, this work assumes a basic understanding of scientific and engineering principles and some familiarity with nuclear power reactors

Thermal-Hydraulics of Water Cooled Nuclear Reactors
Thermal-Hydraulics of Water Cooled Nuclear Reactors

Author: Francesco D'Auria

Publisher: Woodhead Publishing

Published: 2017-05-18

Total Pages: 1200

ISBN-13: 0081006799

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Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants