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

INTERNATIONAL ATOMIC ENERGY AGENCY

Specific Safety Guide

IAEA Safety Standards Series No. SSG-56
Specific Safety Guide

English STI/PUB/1878 | 978-92-0-105719-8

99 pages | 2 figures | € 48.00 | Date published: 2020

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Description

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.

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Keywords

IAEA Safety Standards, NPP, Nuclear Power Plant, Nuclear Facilities, Safety Measures, Safety Fundamentals, Nuclear Installations, Nuclear Safety, Design, Siting, Engineering Safety, Operational Safety, Radiation Safety, Safe Transport, Radioactive Material, Safe Management, Radioactive Waste, Regulatory Body, Evaluation, Management System, International Cooperation, Reactor Coolant System, Heat Removal, Shutdown Conditions, Coolant Inventory, Operational States, Core Reactivity, Control of Core Reactivity, Core Cooling, Residual Heat Removal, Accident Conditions, Heat Sink, Plant States, PIE, Postulated Initiating Events, Internal Hazards, External Hazards, Safety Classification, Environmental Qualification, Calibration, Testing, Maintenance, Inspection, Monitoring, Overpressure Protection, Radiation Protection, Venting, Draining, Containment Isolation, Structural Design, Design Limits, Cooling Conditions, Pressure Control, Pressure Tests, PWR, Pressurized Light Water Reactor, BWR, Boiling Water Reactor, PHWR, Pressurized Heavy Water Reactor, Safety