Accession Number : AD0664460

Title :   THE TENSILE PROPERTIES OF SELECTED STEELS FOR USE IN NUCLEAR REACTOR PRESSURE VESSELS.

Descriptive Note : Phase I of final rept.,

Corporate Author : NAVAL RESEARCH LAB WASHINGTON D C

Personal Author(s) : Klier,Eugene P. ; Hawthorne,J. R. ; Steele,Lendell E.

Report Date : 26 DEC 1967

Pagination or Media Count : 59

Abstract : Seven steels now used or having potential for use in the construction of nuclear reactor containment vessels were evaluated in uniaxial tension at 75F following irradiation at <250F. Experiment irradiations involved neutron fluences up to 9.5 x 10 to the 19th power n/cm sq. (> 1Mev). Tensile properties of the A212-B, A302-B, A350-LF1 (Modified), A350-LF3, A353, T-1, and HY-80 (Ni-Cr-Mo) steels were determined as conventional tensile and yield strength and percent reduction of area. In addition, observed stress-strain relationships were plotted using both nominal stress-percent reduction of area coordinates and true stress-natural strain coordinates. Curves given in the latter coordinate system were also expressed in suitable analytic form. All individual tensile data were compiled in tabular form, and stress-strain curves were summarized as bands giving maximum and minimum properties behavior. Limited metallographic and fractographic data were obtained to establish the metallurgical structures of the steels and to depict the transition from a ductile shear fracture to a brittle flat fracture at high neutron fluences for the more brittle steels. (Author)

Descriptors :   (*STEEL, TENSILE PROPERTIES), (*NUCLEAR REACTORS, STEEL), (*PRESSURE VESSELS, NUCLEAR REACTORS), SHEAR STRESSES, FRACTURE(MECHANICS), STRAIN(MECHANICS), NEUTRONS, METALLOGRAPHY, BRITTLENESS, MICROSTRUCTURE, DAMAGE, RADIATION EFFECTS, TRANSITION TEMPERATURE, FRACTOGRAPHY, DUCTILITY

Subject Categories : Properties of Metals and Alloys
      Nuclear Fission Reactors(non-power)

Distribution Statement : APPROVED FOR PUBLIC RELEASE