SM-1 Reactor Vessel Closure Stud Investigation (open access)

SM-1 Reactor Vessel Closure Stud Investigation

Abstract: This report presents metallurgical .analyses and corrosion tests conducted to determine :causes of failure of two SM- 1 reactor vessel studs due to fracture in the threaded areas, after 23 months' operation (March 1959). Conclusions of corrosion tests are: (1) failure of the studs was caused by stress corrosion cracking, (2) contributing factors to failure of the studs were improper control of heat treatment of the studs and absence of treatment for stress relief after thread grinding operation.
Date: March 23, 1962
Creator: Reali, D. L.
System: The UNT Digital Library
Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants (open access)

Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants

Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and the results of non-destructive and destructive metallographic analyses.
Date: January 23, 1962
Creator: Haraway, E. S. & Saccocio, R. M.
System: The UNT Digital Library