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| LEADER |
00000cam a2200000Mu 4500 |
| 001 |
EBSCO_on1319221069 |
| 003 |
OCoLC |
| 005 |
20231017213018.0 |
| 006 |
m o d |
| 007 |
cr cnu---unuuu |
| 008 |
221015s2019 xx o ||| 0 eng d |
| 040 |
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|a EBLCP
|b eng
|c EBLCP
|d N$T
|d EBLCP
|d OCLCF
|d OCLCQ
|d OCLCO
|
| 020 |
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|a 9201072228
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| 020 |
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|a 9789201072221
|q (electronic bk.)
|
| 035 |
|
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|a (OCoLC)1319221069
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| 050 |
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4 |
|a TH4581
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| 082 |
0 |
4 |
|a 621.4832
|2 23
|
| 049 |
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|a UAMI
|
| 100 |
1 |
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|a IAEA.
|
| 245 |
1 |
0 |
|a Design of the Reactor Containment and Associated Systems for Nuclear Power Plants
|h [electronic resource] :
|b Specific Safety Guide.
|
| 260 |
|
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|a Havertown :
|b International Atomic Energy Agency,
|c 2019.
|
| 300 |
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|a 1 online resource (92 p.).
|
| 490 |
1 |
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|a IAEA Safety Standards Ser. ;
|v v.SSG-53
|
| 500 |
|
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|a Description based upon print version of record.
|
| 505 |
0 |
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|a 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
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| 505 |
8 |
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|a 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
|
| 505 |
8 |
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|a 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
|
| 505 |
8 |
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|a 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
|
| 505 |
8 |
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|a 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
|
| 500 |
|
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|a Periodic testing of the containment leak rate
|
| 590 |
|
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|a eBooks on EBSCOhost
|b EBSCO eBook Subscription Academic Collection - Worldwide
|
| 650 |
|
0 |
|a Nuclear power plants
|x Design and construction.
|
| 650 |
|
6 |
|a Centrales nucléaires
|x Conception et construction.
|
| 650 |
|
7 |
|a Nuclear power plants
|x Design and construction
|2 fast
|
| 776 |
0 |
8 |
|i Print version:
|a IAEA
|t Design of the Reactor Containment and Associated Systems for Nuclear Power Plants
|d Havertown : International Atomic Energy Agency,c2019
|
| 830 |
|
0 |
|a IAEA Safety Standards Ser.
|
| 856 |
4 |
0 |
|u https://ebsco.uam.elogim.com/login.aspx?direct=true&scope=site&db=nlebk&AN=3282270
|z Texto completo
|
| 938 |
|
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|a ProQuest Ebook Central
|b EBLB
|n EBL6985990
|
| 938 |
|
|
|a EBSCOhost
|b EBSC
|n 3282270
|
| 994 |
|
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|a 92
|b IZTAP
|
