S.C Liu(Research Institute for Fracture Technology Faculty of Engineering
,
Tohoku University
,
Sendai
,
Japan
,
on leave from Dalian Railway Institute
,
Dalian 116028
,
China)II-Hyun Kown
,
T Hashida and H Takahashi(Research Institute for nacture Technology
,
Faculty of Engineering
,
Tohoku Univeristy
,
Sendai
,
Japan)
金属学报(英文版)
In order to evaluate the tendency of mechanical properties degrudation due to weld-ing and other processing in materials used for supporting coils in super conducting rnaguets utilized in thermonuclear jusion reactore, a small punch (SP) test was used.This test, which was originally developed to study irradiation damage using miniatursized specimens was performed at 77 and 4 K for solution treated and sensitized JN1 austenitic stainless steel, a candidate cryogenic structural material. The area under the load-deflection curve up to the maximum applied load in SP test was defined as the SP enerpy, to characterize the resistance to fracture. Although solution treated material exhibited ductile fracture mode with high SP enerpy, embrittlement behavior due to sensitization at 650-800°for 1-5 h was shown clearlg by SP test with brittle intergranular fracture and decreased SP enerpy. Comparison of the results obtained by SP test with those by fracture toughness test showed the usefulness of SP test for evaluation of sensitization induced embrittlement at cryogenic temperature. The re-sults obtained in this study can be very usefol in predicting the degradation due to welding and other processing in cryogenic materials.
关键词:
small punch test
,
null
,
null
,
null
