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Current State of Research on Pressurized Water Reactor Safety.
For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-co...
| Clasificación: | Libro Electrónico |
|---|---|
| Autor principal: | |
| Otros Autores: | |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
Les Ulis :
EDP Sciences,
2018.
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| Colección: | Institut de Radioprotection et de Sureté Nucléaire Ser.
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| Temas: | |
| Acceso en línea: | Texto completo |
MARC
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| 100 | 1 | |a Couturier, Jean. | |
| 245 | 1 | 0 | |a Current State of Research on Pressurized Water Reactor Safety. |
| 260 | |a Les Ulis : |b EDP Sciences, |c 2018. | ||
| 300 | |a 1 online resource (228 pages) | ||
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| 490 | 1 | |a Institut de Radioprotection et de Sureté Nucléaire Ser. | |
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| 505 | 0 | |a Intro; Current State of Research on Pressurized Water Reactor Safety; Preface; The authors; List of abbreviations; Glossary of institutions; Technical glossary; Foreword; Contents; Chapter 1: Introduction; Research carried out as part of strategic guidelines and programs; Reference; Chapter 2: Some of the Research Facilities Favored by IRSN in the Field of Nuclear Power Reactor Safety; 2.1 The CABRI reactor; 2.2 The PHEBUS reactor; 2.3 The GALAXIE experimental facility; DIVA (Fire, Ventilation and Airborne Contamination Device); SATURNE; 2.4 Other facilities. | |
| 505 | 8 | |a The CALIST experimental facility (Saclay)The TOSQAN facility (Saclay); The CHIP facility (Cadarache); The EPICUR facility (Cadarache); The IRMA Irradiator (Saclay); Chapter 3: Research on Loss-of-coolant Accidents; 3.1 Two-phase thermal-hydraulics; 3.2 Fuel rod behavior; References; Chapter 4: Research on Reactivity-initiated Accidents; References; Chapter 5: Research on Recirculation Cooling under Accident Conditions; 5.1 Operating experience feedback and research topics; Characterization of debris likely to reach the strainers; Debris transport to strainers. | |
| 505 | 8 | |a Assessment of strainer head loss and clogging riskImpact of chemical effects on strainer head loss; Downstream effects; 5.2 Past research programs and lessons learned; 5.3 Ongoing research programs; 5.4 Simulation; References; Chapter 6: Research on Spent Fuel Pool Uncovery Accidents; Planned programs; References; Chapter 7: Research on Fires; 7.1 Fire risks at nuclear installations; 7.2 Organizations involved in research on fire; 7.3 Research facilities, simulation tools; 7.4 The main research programs and their contributions; References. | |
| 505 | 8 | |a Chapter 8: Research on Hazards associated to Natural Events8.1 Earthquakes; 8.2 External flooding; References; Chapter 9: Research on Core Melt Accidents; 9.1 Heating of the core and core melt inside the vessel; 9.2 Reactor vessel melt-through and basemat erosion by the molten corium; Possibility of in-vessel corium retention; 9.3 Dynamic loading of the containment by a sudden increase in internal pressure; 9.3.1 Steam explosions; 9.3.2 Hydrogen-related risks; 9.3.3 Direct containment heating; 9.4 Radioactive releases; 9.4.1 Emission of radioactive products by fuel. | |
| 505 | 8 | |a 9.4.2 Transporting of radioactive products into the reactor's circuits9.4.3 Radioactive product behavior in the containment; 9.4.4 Contribution of the Phebus-FP program on the various processes involved in radioactive releases; 9.4.5 Aspects to be explored; A) Iodine-related and ruthenium-related aspects; B) Filtration of atmospheric releases; C) A ""water-borne release"" counter-measure to be explored; References; Chapter 10: Research on the Behavior of Components Important to the Safety of NPPs and More Particularly the Aging of Such Components; 10.1 R & D on metallic components. | |
| 500 | |a 10.1.1 Research on thermal fatigue. | ||
| 520 | |a For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally. This publication reflects IRSN's desire to keep an enduring record of its results and to share its knowledge. | ||
| 590 | |a ProQuest Ebook Central |b Ebook Central Academic Complete | ||
| 650 | 0 | |a Water cooled reactors. | |
| 650 | 0 | |a Nuclear reactors |x Security measures. | |
| 650 | 0 | |a Nuclear reactors |x Safety measures. | |
| 650 | 6 | |a Réacteurs refroidis par eau. | |
| 650 | 6 | |a Réacteurs nucléaires |x Sécurité |x Mesures. | |
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| 650 | 7 | |a Nuclear reactors |x Security measures |2 fast | |
| 650 | 7 | |a Water cooled reactors |2 fast | |
| 700 | 1 | |a Schwarz, Michel. | |
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| 830 | 0 | |a Institut de Radioprotection et de Sureté Nucléaire Ser. | |
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