SYMPOSIA PAPER Published: 01 January 1976
STP38044S

Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel

Source

Tension tests were performed on annealed Type 304 stainless steel specimens sectioned from Experimental Breeder Reactor-II (EBR-II) duct thimbles. The specimens had accumulated neutron fluences of up to 10.3 × 1022 neutrons (n)/cm2, E > 0.1 MeV (10.3 × 1026 n/m2, E ×16 fJ). Irradiation temperatures for the material tested ranged from 700 to 750°F (644 to 672 K). The tests were performed at temperatures of room temperature to 1400°F (1033 K), employing strain rates of 2 × 10-3 to 2/min (3.3 × 10-5 to 3.3 × 10-2/s).

At test temperatures below 800°F (700 K), the strength increased with fluence until about 7 × 1022 n/cm2 (7 × 1026 n/m2), beyond which no further increase was observed. The elongation decreased with fluence, reaching levels as low as 0.5 percent uniform and 1.3 percent total elongation at 700°F (644 K). High-fluence failures below 800°F (700 K) occurred by transgranular channel fracture.

At test temperatures above 1000°F (811 K), elongations were reduced to very low levels at high fluences (average total elongation (TE) = 0.03 percent). Extensive intergranular fracture at the high fluences produced the low ductility and resulted in failure of the specimens before reaching the strength characteristic of the true hardness of the material.

Author Information

Fish, RL
Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.
Hunter, CW
Hanford Engineering Development Laboratory, Westinghouse Hanford Company, Richland, Wash.
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Details
Developed by Committee: E10
Pages: 119–138
DOI: 10.1520/STP38044S
ISBN-EB: 978-0-8031-5543-5
ISBN-13: 978-0-8031-0388-7