01734oam 2200445 a 450 991069974090332120101201104721.0(CKB)5470000002405538(OCoLC)688480187(EXLCZ)99547000000240553820101201d2010 ua 0engurbn|||||||||txtrdacontentcrdamediacrrdacarrierSCDAP/RELAP5 thermal-hydraulic evaluations of the potential for containment bypass during extended station blackout severe accident sequences in a Westinghouse four-loop PWR[electronic resource] /prepared by C.D. Fletcher ... [and others]Wash9ngton, DC :U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,[2010]1 online resource (246 unnumbered pages) illustrationsTitle from PDF title screen (viewed on Dec. 1, 2010).."NUREG.CR-6995.""C. Boyd, NRC point of contact.""Manuscript completed: February 2010 ; date published: March 2010.""NRC job code Y6198."Includes bibliographical references.Nuclear power plantsElectric power failuresPressurized water reactorsAccidentsNuclear power plants.Electric power failures.Pressurized water reactorsAccidents.Fletcher C. Don1405089U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.GPOGPOGPOBOOK9910699740903321SCDAP3480973UNINA