Current State of Research on Pressurized Water Reactor Safety.

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Bibliographic Details
Author / Creator:Couturier, Jean.
Imprint:Les Ulis : EDP Sciences, 2018.
Description:1 online resource (228 pages)
Series:Institut de Radioprotection et de Sureté Nucléaire Ser.
Institut de Radioprotection et de Sureté Nucléaire Ser.
Subject:Water cooled reactors.
Nuclear reactors -- Security measures.
Nuclear reactors -- Security measures.
Water cooled reactors.
Electronic books.
Electronic books.
Format: E-Resource Book
URL for this record:
Hidden Bibliographic Details
Other authors / contributors:Schwarz, Michel.
Notes:10.1.1 Research on thermal fatigue.
Print version record.
Other form:Print version: Couturier, Jean. Current State of Research on Pressurized Water Reactor Safety. Les Ulis : EDP Sciences, ©2018 9782759821655
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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. 
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