01461nam 2200373 450 991071595320332120210412113751.0(CKB)5470000002516563(OCoLC)1245856895(EXLCZ)99547000000251656320210412d1980 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAdditional guidance on "Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports"[Washington, D.C ] :[U.S. Nuclear Regulatory Commission],1980.1 online resourceGeneric letter ;80-47"May 20, 1980."Additional guidance on "Potential for low fracture toughness and lamellar tearing on pressurized water reactor steam generator and reactor coolant pump supports"Pressurized water reactorsNuclear reactorsMaterialsTestingPressurized water reactors.Nuclear reactorsMaterialsTesting.U.S. Nuclear Regulatory Commission,GPOGPOGPOBOOK9910715953203321Additional guidance on "Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports"3270344UNINA