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| LEADER |
00000cam a2200000Mu 4500 |
| 001 |
EBSCO_on1319213923 |
| 003 |
OCoLC |
| 005 |
20231017213018.0 |
| 006 |
m o d |
| 007 |
cr cnu---unuuu |
| 008 |
221015s2020 xx o ||| 0 eng d |
| 040 |
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|a EBLCP
|b eng
|c EBLCP
|d N$T
|d EBLCP
|d OCLCQ
|d N$T
|d OCLCQ
|d OCLCF
|d OCLCQ
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| 020 |
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|a 9201064225
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| 020 |
|
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|a 9789201064226
|q (electronic bk.)
|
| 035 |
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|a (OCoLC)1319213923
|
| 050 |
|
4 |
|a TK9212
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| 082 |
0 |
4 |
|a 621.4835
|2 23/eng/20230112
|
| 049 |
|
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|a UAMI
|
| 100 |
1 |
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|a IAEA.
|
| 245 |
1 |
0 |
|a Design of the Reactor Coolant System 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 2020.
|
| 300 |
|
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|a 1 online resource (102 p.).
|
| 490 |
1 |
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|a IAEA Safety Standards Ser. ;
|v v.SSG-56
|
| 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. 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
|
| 505 |
8 |
|
|a 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
|
| 505 |
8 |
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|a 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
|
| 505 |
8 |
|
|a 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
|
| 505 |
8 |
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|a 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)
|
| 500 |
|
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|a Reactor coolant pumps (for PWRs and PHWRs) and reactor recirculation pumps (for BWRs)
|
| 590 |
|
|
|a eBooks on EBSCOhost
|b EBSCO eBook Subscription Academic Collection - Worldwide
|
| 650 |
|
0 |
|a Nuclear power plants
|x Design and construction.
|
| 650 |
|
0 |
|a Nuclear reactors
|x Cooling.
|
| 650 |
|
0 |
|a Nuclear power plants
|x Safety measures.
|
| 650 |
|
7 |
|a Nuclear power plants
|x Design and construction.
|2 fast
|0 (OCoLC)fst01040481
|
| 650 |
|
7 |
|a Nuclear power plants
|x Safety measures.
|2 fast
|0 (OCoLC)fst01040645
|
| 650 |
|
7 |
|a Nuclear reactors
|x Cooling.
|2 fast
|0 (OCoLC)fst01040765
|
| 776 |
0 |
8 |
|i Print version:
|a IAEA
|t Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants
|d Havertown : International Atomic Energy Agency,c2020
|
| 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=3282288
|z Texto completo
|
| 938 |
|
|
|a ProQuest Ebook Central
|b EBLB
|n EBL6986001
|
| 938 |
|
|
|a ProQuest Ebook Central
|b EBLB
|n EBL6986001
|
| 938 |
|
|
|a EBSCOhost
|b EBSC
|n 3282288
|
| 994 |
|
|
|a 92
|b IZTAP
|
