Download Free Ultimate Heat Sink And Directly Associated Heat Transport Systems For Nuclear Power Plants Book in PDF and EPUB Free Download. You can read online Ultimate Heat Sink And Directly Associated Heat Transport Systems For Nuclear Power Plants and write the review.

The ultimate heat sink and its directly associated heat transport systems addressed in this guide are required to remove residual heat from the core after reactor shutdown, and during and after appropriate operational states and accident conditions.
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.
This publication is a revision and combinaton 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 and Safety Series No. 50-SG-D13, Reactor Coolant and Associated Systems in Nuclear Power Plants (1986), which are superseded by this new Safety Guide. 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 in 1981 and 1986, respectively. The other objectives of the revision are to ensure consistency with the Requirements for Design, issued in 2000, and to update the technical content. In addition, an appendix on pressurized heavy water reactors has been included.
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.
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.
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.

Nuclear Plant Shutdowns

United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment

Published: 1980

Total Pages: 388


Get eBook