Design of the Reactor Core for Nuclear Power Plants: Specific Safety Guide.
Gespeichert in:
| Körperschaft: | |
|---|---|
| Format: | Elektronisch E-Book |
| Sprache: | English |
| Veröffentlicht: |
Vienna :
International Atomic Energy Agency,
2005.
|
| Schriftenreihe: | Safety standards series ;
no. NS-G-1.12. |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Beschreibung: | Description based upon print version of record. |
| Beschreibung: | 1 online resource (78 p.). |
| Bibliographie: | Includes bibliographical references. |
| ISBN: | 9201076223 9789201076229 |
| ISSN: | 1020-525X ; |
Internformat
MARC
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| 110 | 2 | |a International Atomic Energy Agency. |0 http://id.loc.gov/authorities/names/n79053681 | |
| 245 | 1 | 0 | |a Design of the Reactor Core for Nuclear Power Plants |h [electronic resource] : |b Specific Safety Guide. |
| 260 | |a Vienna : |b International Atomic Energy Agency, |c 2005. | ||
| 300 | |a 1 online resource (78 p.). | ||
| 490 | 1 | |a IAEA safety standards, |x 1020-525X ; |v no. NS-G-1.12 | |
| 500 | |a Description based upon print version of record. | ||
| 504 | |a Includes bibliographical references. | ||
| 505 | 0 | |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 | |
| 505 | 8 | |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 | |
| 505 | 8 | |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 | |
| 505 | 8 | |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 | |
| 650 | 0 | |a Nuclear reactors |x Design and construction. |0 http://id.loc.gov/authorities/subjects/sh85093082 | |
| 650 | 0 | |a Nuclear power plants |x Safety measures. | |
| 650 | 6 | |a Réacteurs nucléaires |x Conception et construction. | |
| 650 | 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 |
| 830 | 0 | |a Safety standards series ; |v no. NS-G-1.12. |0 http://id.loc.gov/authorities/names/no99051531 | |
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| 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 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 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 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 |
| ctrlnum | (OCoLC)1319220077 |
| dewey-full | 621.48/35 |
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| dewey-search | 621.48/35 |
| dewey-sort | 3621.48 235 |
| dewey-tens | 620 - Engineering and allied operations |
| discipline | Energietechnik |
| format | Electronic eBook |
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| id | ZDB-4-EBA-on1319220077 |
| illustrated | Not Illustrated |
| indexdate | 2024-10-25T15:51:18Z |
| institution | BVB |
| institution_GND | http://id.loc.gov/authorities/names/n79053681 |
| isbn | 9201076223 9789201076229 |
| issn | 1020-525X ; |
| language | English |
| oclc_num | 1319220077 |
| open_access_boolean | |
| owner | MAIN |
| owner_facet | MAIN |
| physical | 1 online resource (78 p.). |
| psigel | ZDB-4-EBA |
| publishDate | 2005 |
| publishDateSearch | 2019 |
| publishDateSort | 2019 |
| publisher | International Atomic Energy Agency, |
| record_format | marc |
| series | Safety standards series ; |
| series2 | IAEA safety standards, |
| spelling | International Atomic Energy Agency. http://id.loc.gov/authorities/names/n79053681 Design of the Reactor Core for Nuclear Power Plants [electronic resource] : Specific Safety Guide. Vienna : International Atomic Energy Agency, 2005. 1 online resource (78 p.). IAEA safety standards, 1020-525X ; no. NS-G-1.12 Description based upon print version of record. Includes bibliographical references. 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 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 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 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 Nuclear reactors Design and construction. http://id.loc.gov/authorities/subjects/sh85093082 Nuclear power plants Safety measures. Réacteurs nucléaires Conception et construction. Centrales nucléaires Sécurité Mesures. Nuclear power plants Safety measures fast Nuclear reactors Design and construction fast Print version: IAEA Design of the Reactor Core for Nuclear Power Plants Havertown : International Atomic Energy Agency,c2019 Safety standards series ; no. NS-G-1.12. http://id.loc.gov/authorities/names/no99051531 FWS01 ZDB-4-EBA FWS_PDA_EBA https://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&AN=3282273 Volltext CBO01 ZDB-4-EBA FWS_PDA_EBA https://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&AN=3282273 Volltext |
| spellingShingle | Design of the Reactor Core for Nuclear Power Plants Specific Safety Guide. Safety standards series ; 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 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 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 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 Nuclear reactors Design and construction. http://id.loc.gov/authorities/subjects/sh85093082 Nuclear power plants Safety measures. Réacteurs nucléaires Conception et construction. Centrales nucléaires Sécurité Mesures. Nuclear power plants Safety measures fast Nuclear reactors Design and construction fast |
| subject_GND | http://id.loc.gov/authorities/subjects/sh85093082 |
| title | Design of the Reactor Core for Nuclear Power Plants Specific Safety Guide. |
| title_auth | Design of the Reactor Core for Nuclear Power Plants Specific Safety Guide. |
| title_exact_search | Design of the Reactor Core for Nuclear Power Plants Specific Safety Guide. |
| title_full | Design of the Reactor Core for Nuclear Power Plants [electronic resource] : Specific Safety Guide. |
| title_fullStr | Design of the Reactor Core for Nuclear Power Plants [electronic resource] : Specific Safety Guide. |
| title_full_unstemmed | Design of the Reactor Core for Nuclear Power Plants [electronic resource] : Specific Safety Guide. |
| title_short | Design of the Reactor Core for Nuclear Power Plants |
| title_sort | design of the reactor core for nuclear power plants specific safety guide |
| title_sub | Specific Safety Guide. |
| topic | Nuclear reactors Design and construction. http://id.loc.gov/authorities/subjects/sh85093082 Nuclear power plants Safety measures. Réacteurs nucléaires Conception et construction. Centrales nucléaires Sécurité Mesures. Nuclear power plants Safety measures fast Nuclear reactors Design and construction fast |
| topic_facet | Nuclear reactors Design and construction. Nuclear power plants Safety measures. Réacteurs nucléaires Conception et construction. Centrales nucléaires Sécurité Mesures. Nuclear power plants Safety measures Nuclear reactors Design and construction |
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