Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants Specific Safety Guide.
- Havertown : International Atomic Energy Agency, (c)2020.
- 1 online resource (102 pages).
- IAEA Safety Standards Ser. ; v.SSG-56 .
Description based upon print version of record. Reactor coolant pumps (for PWRs and PHWRs) and reactor recirculation pumps (for BWRs)
Includes bibliographies and index.
Intro -- 1. INTRODUCTION -- Background -- Objective -- Scope -- Structure -- 2. Extent of the reactor coolant system and associated systems -- Reactor coolant system -- Systems for heat removal in shutdown conditions -- Systems for coolant inventory control in operational states -- Systems for control of core reactivity in operational states -- Systems for core cooling and residual heat removal in accident conditions -- Systems for control of core reactivity in accident conditions -- Ultimate heat sink and residual heat transfer systems in all plant states 3. DESIGN BASIS OF THE REACTOR COOLANT SYSTEM AND ASSOCIATED SYSTEMS -- General -- Safety functions -- Postulated initiating events -- Internal hazards -- External hazards -- Accident conditions -- Design basis accidents -- Design extension conditions without significant fuel degradation -- Design limits and acceptance criteria -- Reliability -- Systems designed to cope with design basis accidents -- Safety features for design extension conditions without significant fuel degradation -- Defence in depth -- Safety classification -- Environmental qualification of items important to safety Loads and load combinations -- Materials -- Materials in contact with radioactive fluids -- Materials exposed to high neutron flux -- Manufacturing and installation -- Calibration, testing, maintenance, repair, replacement, inspection and monitoring -- Pre-service and in-service inspection of the reactor coolant system -- Inspection of steam generators -- Overpressure protection -- Layout -- Radiation protection -- Combustible gas accumulation in normal operation -- Venting and draining -- Interfaces between the reactor coolant system and associated systems -- Containment isolation Instrumentation -- Multiple units at a site -- Codes and standards -- Use of probabilistic analyses in design -- 4. ULTIMATE HEAT SINK AND RESIDUAL HEAT TRANSFER SYSTEMS -- Ultimate heat sink -- Residual heat transfer systems -- Residual heat transfer in operational states -- Residual heat transfer for design basis accidents -- Residual heat transfer for design extension conditions -- 5. SPECIFIC CONSIDERATIONS IN DESIGN OF THE REACTOR COOLANT SYSTEM -- Structural design -- Design basis loads and load combinations -- Control of cooling conditions in operational states Pressure control and overpressure protection -- Isolation of the reactor coolant pressure boundary -- Postulated initiating events -- Internal hazards -- External hazards -- Layout -- Design limits -- Safety classification -- Environmental qualification -- Pressure tests -- Venting -- For pressurized water reactors -- For boiling water reactors -- For pressurized heavy water reactors -- Specific design aspects -- Reactor pressure vessel -- Reactor pressure vessel internals (for PWRs and BWRs) -- Fuel channel assemblies (for PHWRs)
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Nuclear power plants--Design and construction. Nuclear reactors--Cooling. Nuclear power plants--Safety measures.