000			05218cam a2200613Mi 4500
001			on1028955613
003			OCoLC
005			20220517104411.0
006			m d
007			cr |n|---|||||
008			180317s2018 xx o 000 0 eng d
040			_aEBLCP _beng _epn _erda _cEBLCP _dYDX _dOCLCQ _dIDB _dOCLCF _dVT2 _dN$T
019			_a1028847431 _a1028896185
020			_a9782759821655 _q(electronic bk.)
020			_a275982165X _q(electronic bk.)
035			_a1725050 _b(N$T)
035			_a(OCoLC)1028955613 _z(OCoLC)1028847431 _z(OCoLC)1028896185
050		4	_aTK9203.W37 _b.C688 2018eb
072		7	_aTEC _x009070 _2bisacsh
082	0	4	_a621.4831 _223
049			_aMAIN
100	1		_aCouturier, Jean, _eauthor _932993
245	1	0	_aCurrent State of Research on Pressurized Water Reactor Safety _h[electronic resource].
264		1	_aLes Ulis : _bEDP Sciences, _c2018.
300			_a1 online resource (228 pages).
336			_atext _btxt _2rdacontent
337			_acomputer _bc _2rdamedia
338			_aonline resource _bcr _2rdacarrier
490	1		_aInstitut de Radioprotection et de Sureté Nucléaire Ser.
588	0		_aPrint version record.
505	0		_aIntro; 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		_aThe 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		_aAssessment 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		_aChapter 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		_a9.4.2 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 and D on metallic components.
500			_a10.1.1 Research on thermal fatigue.
590			_aAdded to collection customer.56279.3 - Master record variable field(s) change: 072
650		0	_aWater cooled reactors. _932994
650		0	_aNuclear reactors _xSecurity measures. _932995
650		7	_aNuclear reactors _xSecurity measures. _2fast _0(OCoLC)fst01040857 _932995
650		7	_aWater cooled reactors. _2fast _0(OCoLC)fst01171668 _932994
650		7	_aTECHNOLOGY & ENGINEERING / Mechanical _2bisacsh
655		4	_aElectronic books.
700	1		_aSchwarz, Michel. _932996
776	0	8	_iPrint version: _aCouturier, Jean. _tCurrent State of Research on Pressurized Water Reactor Safety. _dLes Ulis : EDP Sciences, ©2018 _z9782759821655
830		0	_aInstitut de Radioprotection et de Sureté Nucléaire Ser. _932997
856	4	0	_3EBSCOhost _uhttps://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=1725050
938			_aEBL - Ebook Library _bEBLB _nEBL5317419
938			_aYBP Library Services _bYANK _n15219142
938			_aEBSCOhost _bEBSC _n1725050
942			_cEBK
994			_a92 _bN$T
999			_c5684 _d5684