Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants Specific Safety Guide.
IAEA.
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)
9201064225 9789201064226
Nuclear power plants--Design and construction.
Nuclear reactors--Cooling.
Nuclear power plants--Safety measures.
Electronic Books.
TK9212 / .D475 2020
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)
9201064225 9789201064226
Nuclear power plants--Design and construction.
Nuclear reactors--Cooling.
Nuclear power plants--Safety measures.
Electronic Books.
TK9212 / .D475 2020