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Nishiyama, Yutaka; Onizawa, Kunio; Idei, Yoshio; Suzuki, Masahide
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
AbstractAbstract
[en] This paper reports the residual stresses and thermal aging and neutron irradiation embrittlement of stainless steel weld overlay cladding made by electroslag and submerged arc methods on low-alloy pressure vessel base steels. The results of residual stress distribution measurements by layer removal method showed that high tensile stresses and compressive stresses were found in the clad and heat affected zone of the base metal, respectively. Thermal aging at 400degC for 10000 h caused a slight increase in strength, the shift in ductile to brittle transition temperature (DBTT) and the loss of the upper shelf energy (USE). The similar results were obtained in the neutron irradiated cladding to a fluence of 1.5-2.0x1020 n/cm2 (E > 1 MeV). Such hardening and degradation in the Charpy related properties were comparable in electroslag and submerged arc weld overlay cladding, while the initial DBTT and USE in electroslag weld overlay cladding were lower and higher than those in submerged arc weld overlay cladding, respectively. The shift in DBTT due to neutron irradiation in the weld overlay cladding was lower than that in the low-alloy pressure vessel base steels. (author)
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Source
Oct 2000; 39 p; 11 refs., 25 figs., 7 tabs.
Record Type
Report
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Country of publication
ALLOYS, ARC WELDING, CARBON ADDITIONS, CONTAINERS, DEPOSITION, ENRICHED URANIUM REACTORS, FABRICATION, HARDENING, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, JOINING, PHYSICAL RADIATION EFFECTS, POWER REACTORS, RADIATION EFFECTS, REACTORS, SAFETY, STEELS, STRESSES, SURFACE COATING, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS, WELDING
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