Energia i regulacje · 7.06.2016
Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants With Thermally-Treated Alloy 600 and 690 Steam Generator Tubes
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2195, "Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treated Alloy 600 and 690 Steam Generator Tubes." This report summarizes severe accident-induced consequential steam generator tube rupture (C-SGTR) analyses recently performed by the NRC's Office of Nuclear Regulatory Research. The analyses described in this report include risk assessment, thermal- hydraulic analyses, and materials behavior analyses.