01338nam 2200373 450 991071530370332120210312145300.0(CKB)5470000002511002(OCoLC)1241260985(EXLCZ)99547000000251100220210312d1991 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierErrors in main steam line break analyses for determining containment parametersWashington, D.C. :United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation,1991.1 online resourceInformation notice ;no. 91-69"November 1, 1991."Pressurized water reactorsLoss of coolantSteam-boilersFailuresNuclear reactorsContainmentPressurized water reactorsLoss of coolant.Steam-boilersFailures.Nuclear reactorsContainment.U.S. Nuclear Regulatory Commission.Office of Nuclear Reactor Regulation,GPOGPOBOOK9910715303703321Errors in main steam line break analyses for determining containment parameters3303771UNINA