TY  - BOOK
AU  - IAEA
TI  - Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants: Specific Safety Guide
T2  - IAEA Safety Standards Ser.
SN  - 9201064225
AV  - TK9212 .D475 2020
PY  - 2020///
CY  - Havertown
PB  - International Atomic Energy Agency
KW  - Nuclear power plants
KW  - Design and construction
KW  - Nuclear reactors
KW  - Cooling
KW  - Safety measures
KW  - Electronic Books
N1  - Description based upon print version of record; Reactor coolant pumps (for PWRs and PHWRs) and reactor recirculation pumps (for BWRs); 2; 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); 2; b
UR  - httpss://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=3282288&site=eds-live&custid=s3260518
ER  -