Description |
1 online resource (78 pages). |
Physical Medium |
polychrome |
Description |
text file |
Series |
IAEA safety standards,
1020-525X ;
no. NS-G-1.12
|
|
Safety standards series ; no. NS-G-1.12.
|
Note |
Description based upon print version of record. |
Bibliography |
Includes bibliographical references. |
Contents |
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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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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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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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 |
Local Note |
eBooks on EBSCOhost EBSCO eBook Subscription Academic Collection - North America |
Subject |
Nuclear reactors -- Design and construction.
|
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Nuclear reactors -- Design and construction. |
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Nuclear power plants -- Safety measures.
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Nuclear power plants -- Safety measures. |
Other Form: |
Print version: IAEA Design of the Reactor Core for Nuclear Power Plants Havertown : International Atomic Energy Agency,c2019 |
ISBN |
9201076223 |
|
9789201076229 (electronic book) |
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