1993
DOI: 10.1007/bf00774631
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Corrosion-cracking resistance of austenitic stainless steel under stress in an iodine medium

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“…The SCC of zirconium alloys used for nuclear power reactor fuel cladding in iodine, a byproduct of the uranium fission reaction, is a well-documented problem (Cox, 1972;Wood, 1972;Sidky, 1998). While zirconium alloys are widely used as cladding in water-cooled reactors operating at temperatures close to 300°C, studies (Lobb & Jones, 1976;Lobb & Nicholson 1976;Lobb, 1978;Kiselevskii et al, 1993) conducted at 650°C and 750°C report that iodine vapor decreases creep resistance of austenitic stainless steels, a problem relevant for fuel cladding integrity of fast and advanced cooled reactors. Likewise, I 2 and I − can be generated in aqueous homogeneous reactors, where uranium salts are dissolved in an aqueous solution that serves as moderator and coolant (Lillard, 2010).…”
Section: Scc In the Presence Of Iodides And Iodinementioning
confidence: 99%
“…The SCC of zirconium alloys used for nuclear power reactor fuel cladding in iodine, a byproduct of the uranium fission reaction, is a well-documented problem (Cox, 1972;Wood, 1972;Sidky, 1998). While zirconium alloys are widely used as cladding in water-cooled reactors operating at temperatures close to 300°C, studies (Lobb & Jones, 1976;Lobb & Nicholson 1976;Lobb, 1978;Kiselevskii et al, 1993) conducted at 650°C and 750°C report that iodine vapor decreases creep resistance of austenitic stainless steels, a problem relevant for fuel cladding integrity of fast and advanced cooled reactors. Likewise, I 2 and I − can be generated in aqueous homogeneous reactors, where uranium salts are dissolved in an aqueous solution that serves as moderator and coolant (Lillard, 2010).…”
Section: Scc In the Presence Of Iodides And Iodinementioning
confidence: 99%