| Description |
1 online resource (92 pages). |
| Physical Medium |
polychrome |
| Description |
text file |
| Series |
IAEA Safety Standards Ser. ; v.SSG-53
|
|
IAEA Safety Standards Ser.
|
| Note |
Description based upon print version of record. |
| Contents |
Intro -- 1. INTRODUCTION -- Background -- Objective -- Scope -- Structure -- 2. CONTAINMENT SAFETY FUNCTIONS AND THE DESIGN APPROACH -- Safety functions -- Confinement of radioactive material -- Protection against external and internal hazards -- Radiation shielding -- 3. DESIGN BASIS OF THE CONTAINMENT STRUCTURE AND ITS COMPONENTS AND ASSOCIATED SYSTEMS -- General -- Postulated initiating events -- Internal hazards -- External hazards -- Accident conditions -- General -- Design basis accidents -- Design extension conditions -- Design limits -- Reliability |
|
Systems designed to mitigate design basis accidents -- Safety features for design extension conditions without significant fuel degradation -- Safety features for design extension conditions with core melting -- Defence in depth -- Practical elimination of conditions that could lead to an early radioactive release or a large radioactive release -- Safety classification -- Environmental qualification -- Codes and standards -- Use of probabilistic safety analyses in design -- 4. Design of the containment and its associated systems -- General |
|
Layout and configuration of the containment and its associated systems -- Maintenance and accessibility -- Operator actions -- Sharing of parts of the containment systems between units -- Ageing effects -- Decommissioning -- Structural design of containment -- General design process -- Loads and load combinations -- Engineering criteria -- Local stresses and fatigue -- Ultimate capability and failure mode -- Structural design of structures within the containment -- In-vessel retention strategy -- Ex-vessel retention strategy -- Structural design of systems |
|
Mass and energy release and management -- Control of pressure and temperature in operational states -- Control of pressure and temperature in accident conditions -- Control and limitation of radioactive releases -- Containment source term -- Leaktightness of the containment -- Secondary confinement building -- Containment bypass -- Reduction of radioactive material in the containment atmosphere -- Management of combustible gases -- Generation of combustible gases -- Threats due to combustible gases in design extension conditions with core melting |
|
Measures for the mitigation of hydrogen combustion and for the prevention of hydrogen combustion challenging the containment integrity -- Mechanical features of the containment -- Provisions for containment isolation of piping and ducting systems -- Isolation valves -- Penetrations -- Air locks, doors and hatches -- Materials -- Concrete -- Metallic materials -- Soft sealing materials -- Covering, cushioning, thermal insulation and coating materials -- Instrumentation -- Monitoring the stability of the containment -- Detection of deviations from normal operation |
| Note |
Periodic testing of the containment leak rate |
| Local Note |
eBooks on EBSCOhost EBSCO eBook Subscription Academic Collection - North America |
| Subject |
Nuclear power plants -- Design and construction.
|
|
Nuclear power plants -- Design and construction. |
| Other Form: |
Print version: IAEA Design of the Reactor Containment and Associated Systems for Nuclear Power Plants Havertown : International Atomic Energy Agency,c2019 |
| ISBN |
9201072228 |
|
9789201072221 (electronic book) |
|
