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00000cam a22000007a 4500 |
| 001 |
EBSCO_on1319220077 |
| 003 |
OCoLC |
| 005 |
20231017213018.0 |
| 006 |
m o d |
| 007 |
cr cnu---unuuu |
| 008 |
221015s2019 au ob 000 0 eng d |
| 040 |
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|a EBLCP
|b eng
|c EBLCP
|d N$T
|d EBLCP
|d N$T
|d OCLCQ
|d OCLCF
|d OCLCO
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| 020 |
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|a 9201076223
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| 020 |
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|a 9789201076229
|q (electronic bk.)
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| 035 |
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|a (OCoLC)1319220077
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| 050 |
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4 |
|a TK9152
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| 082 |
0 |
4 |
|a 621.48/35
|2 23/eng/20221220
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| 049 |
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|a UAMI
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| 110 |
2 |
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|a International Atomic Energy Agency.
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| 245 |
1 |
0 |
|a Design of the Reactor Core for Nuclear Power Plants
|h [electronic resource] :
|b Specific Safety Guide.
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| 260 |
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|a Vienna :
|b International Atomic Energy Agency,
|c 2005.
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| 300 |
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|a 1 online resource (78 p.).
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| 490 |
1 |
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|a IAEA safety standards,
|x 1020-525X ;
|v no. NS-G-1.12
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| 500 |
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|a Description based upon print version of record.
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| 504 |
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|a Includes bibliographical references.
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| 505 |
0 |
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|a Intro -- 1. INTRODUCTION -- Background -- Objective -- Scope -- Structure -- 2. GENERAL SAFETY CONSIDERATIONS IN THE DESIGN of THE REACTOR CORE -- Management system -- Design objectives -- Fundamental safety functions -- Adequate design based on the concept of defence in depth -- Proven engineering practices -- Safety assessment in the design process -- Features to facilitate radioactive waste management -- Design basis for structures, systems and components of the reactor core -- Plant states and postulated initiating events -- External hazards -- Design limits
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| 505 |
8 |
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|a Safety classification aspects of the reactor core -- Engineering design rules -- Design for reliability -- Operational limits and conditions -- Design for safe operation -- Reactor core safety analysis -- 3. SPECIFIC SAFETY CONSIDERATIONS IN THE DESIGN OF THE REACTOR CORE -- General -- Fuel type -- Coolant -- Moderator -- Neutronic design -- Design considerations -- Nuclear design limits -- Thermohydraulic design -- Design considerations -- Thermohydraulic design limits -- Thermomechanical design of fuel rods and fuel assemblies -- Design considerations -- Fuel design limits
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| 505 |
8 |
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|a Mechanical design of core structures and components -- Design considerations -- Design limits for the mechanical design of core structures and components -- Reactor core control, shutdown and monitoring systems -- Reactor core control system -- Reactor shutdown system -- Partial trip system -- Operating limits and set points -- Core monitoring system -- Core management -- Design considerations -- Core management design limits -- Special core configurations -- Impact of fuel design and core management on fuel handling, transport, storage, reprocessing and disposal -- 4. QUALIFICATION AND TESTING
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| 505 |
8 |
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|a General -- Design qualification -- Inspection -- Testing including prototype assemblies and lead use assemblies -- REFERENCES -- Annex ISUPPLEMENTARY TECHNICAL INFORMATION -- Annex II ASPECTS TO BE ADDRESSED IN THE DESIGN OF THE FUEL ROD, FUEL ASSEMBLY, REACTIVITY CONTROL ASSEMBLY, NEUTRON SOURCE ASSEMBLY AND HYDRAULIC PLUG ASSEMBLY -- CONTRIBUTORS TO DRAFTING AND REVIEW
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| 590 |
|
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|a eBooks on EBSCOhost
|b EBSCO eBook Subscription Academic Collection - Worldwide
|
| 650 |
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0 |
|a Nuclear reactors
|x Design and construction.
|
| 650 |
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0 |
|a Nuclear power plants
|x Safety measures.
|
| 650 |
|
6 |
|a Réacteurs nucléaires
|x Conception et construction.
|
| 650 |
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6 |
|a Centrales nucléaires
|x Sécurité
|x Mesures.
|
| 650 |
|
7 |
|a Nuclear power plants
|x Safety measures
|2 fast
|
| 650 |
|
7 |
|a Nuclear reactors
|x Design and construction
|2 fast
|
| 776 |
0 |
8 |
|i Print version:
|a IAEA
|t Design of the Reactor Core for Nuclear Power Plants
|d Havertown : International Atomic Energy Agency,c2019
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| 830 |
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0 |
|a Safety standards series ;
|v no. NS-G-1.12.
|
| 856 |
4 |
0 |
|u https://ebsco.uam.elogim.com/login.aspx?direct=true&scope=site&db=nlebk&AN=3282273
|z Texto completo
|
| 938 |
|
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|a ProQuest Ebook Central
|b EBLB
|n EBL6985961
|
| 938 |
|
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|a EBSCOhost
|b EBSC
|n 3282273
|
| 994 |
|
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|a 92
|b IZTAP
|
