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A safe analysis of high pressure reactors for polyethylene production by K Chiba T Iwadate
Acceptance criteria for weld defects in the hotbox dome of an advanced gascooled reactor
A Tate and G J Rigg
28 other sections not shown
analysis applied assessment ASTM austenitic axial bainitic behaviour bend brittle fracture calculated cent Charpy Charpy impact test cooling corner crack crack front crack propagation crack tip creep critical curve cyclic da/dN defect deﬁned determined displacement ductile dynamic fracture toughness effect equation evaluation experimental F ig failure fatigue crack growth ﬁeld ﬁgure ﬁnite element ﬁrst ﬂange ﬂaw fracture mechanics fracture toughness geometry heat treatment hydrogen hydrogen embrittlement increases inﬂuence ingot initiation lateral expansion linear elastic load martensitic material maximum mechanical properties method notch nozzle nuclear obtained parameter pipe predicted present pressure vessel procedure range ratio reactor residual stress shown in Fig shows signiﬁcant speciﬁed specimens stainless steel strain rate stress intensity factor stress relieved structure surface crack Table tensile tensile strength thermal shock thickness toughness values ture upper shelf weld metal wide plate yield strength zone