Current State of Research on Pressurized Water Reactor Safety.
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| Author / Creator: | Couturier, Jean. |
|---|---|
| Imprint: | Les Ulis : EDP Sciences, 2018. |
| Description: | 1 online resource (228 pages) |
| Language: | English |
| 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. TECHNOLOGY & ENGINEERING -- Mechanical. Nuclear reactors -- Security measures. Water cooled reactors. Electronic books. Electronic books. |
| Format: | E-Resource Book |
| URL for this record: | http://pi.lib.uchicago.edu/1001/cat/bib/12018766 |
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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) | ||
| 336 | |a text |b txt |2 rdacontent | ||
| 337 | |a computer |b c |2 rdamedia | ||
| 338 | |a online resource |b cr |2 rdacarrier | ||
| 490 | 1 | |a Institut de Radioprotection et de Sureté Nucléaire Ser. | |
| 588 | 0 | |a Print version record. | |
| 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. | ||
| 650 | 0 | |a Water cooled reactors. |0 http://id.loc.gov/authorities/subjects/sh85145547 | |
| 650 | 0 | |a Nuclear reactors |x Security measures. | |
| 650 | 7 | |a TECHNOLOGY & ENGINEERING |x Mechanical. |2 bisacsh | |
| 650 | 7 | |a Nuclear reactors |x Security measures. |2 fast |0 (OCoLC)fst01040857 | |
| 650 | 7 | |a Water cooled reactors. |2 fast |0 (OCoLC)fst01171668 | |
| 655 | 0 | |a Electronic books. | |
| 655 | 4 | |a Electronic books. | |
| 700 | 1 | |a Schwarz, Michel. | |
| 776 | 0 | 8 | |i Print version: |a Couturier, Jean. |t Current State of Research on Pressurized Water Reactor Safety. |d Les Ulis : EDP Sciences, ©2018 |z 9782759821655 |
| 830 | 0 | |a Institut de Radioprotection et de Sureté Nucléaire Ser. | |
| 856 | 4 | 0 | |u https://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&AN=1725050 |y eBooks on EBSCOhost |
| 856 | 4 | 0 | |u https://search.ebscohost.com/login.aspx?direct=true&scope=site&db=e000xna&AN=1725050 |y eBooks on EBSCOhost |
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