Published September 1967 | Version v1
Report Open

Irradiation Effects at 160-240 deg C in Some Swedish Pressure Vessel Steels

  • 1. AB Atomenergi, Nykoeping (Sweden)
  • 2. Chalmers Institute of Technology, Goeteborg (Sweden)
  • 3. Motala Verkstads AB, Motala (Sweden)

Description

Tensile specimens, Charpy impact specimens and miniature impact specimens of six steels in different conditions were irradiated to 2.8 x 1018 and 5.6 x 1018 n/cm2 (> 1 MeV) at 160-240 deg C. The steels investigated were SIS 142103, 2103/R3, NO 345, Fortiweld, Fortiweld HS and OK 54 P. There is no correlation between the increase in transition temperature and initial transition temperature. However, changes in strength and ductility can be correlated to the initial yield strength. The increases in transition temperature due to strain aging and irradiation are approximately additive. The irradiation-induced changes in 2103/R3 and Fortiweld HS steels do not vary with position in the thickness of the plate. Different tempering treatments in Fortiweld HS steel do not change the extent of irradiation effects. Normal Charpy V-notch impact specimens and miniature specimens give the same irradiation-induced increase in transition temperature

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Additional details

Publishing Information

Imprint Pagination
44 p.
Report number
AE--298

Optional Information

Notes
14 refs., 20 figs., 4 tabs.