Swelling, mechanical properties and structure of austenitic high-nickel alloy irradiated in a fast reactor

Conference · Mon Dec 30 23:00:00 EST 1996

OSTI ID:524835

Shamardin, V K; Neustroev, V S; Povstyanko, A V; Bulanova, T M; Ostrovsky, Z E ^[1]; Kuznetzov, A A; Kursevitch, I P; Nikolaev, V A ^[2]

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1. Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation)
2. Central Research Inst. of Structural Materials, St. Petersburg (Russian Federation)

Specimens from fuel assembly wrappers and control rod cases of 0.07C-15Cr35Ni-3Mo-B-Zr-Y alloy were investigated after irradiation in the BOR-60 and BN-600 reactors up to a maximum damage dose of about 110 dpa at temperatures between 340 to 550 C. Maximum swelling occurs at 420 to 430 C with 6% at a dose of about 80 dpa and 13.5% at a dose of 108 dpa. The maximum change in strength properties and corresponding decrease of ductility occur at an irradiation temperature of 385 C. With increasing testing temperature the ductility increases from 3--6% up to 22% at 450 C for the material irradiated at 60--80 dpa. Frank dislocation loops with an average diameter of 25 nm voids having diameter between 20 to 23 nm and semicoherent needle-like precipitates with an average length of 21 nm, oriented to several directions, were observed in the alloy structure irradiated to 60 dpa at 430 C. Analysis of the experimental data was performed and the service life time of the investigated alloy was estimated for use as a material for control rod cases of the BOR-60 reactor.

• OSTI ID: 524835
• Report Number(s): CONF-940657--
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
BELOYARSK-3 REACTOR
BOR-60 REACTOR
CRYSTAL STRUCTURE
LOW CARBON-HIGH ALLOY STEELS
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
REACTOR MATERIALS
SWELLING