SYMPOSIA PAPER Published: 01 January 1981
STP28222S

Tensile Properties of Neutron-Irradiated Nimonic PE16

Source

Tension specimens of Nimonic PE16 in the solution-treated and aged condition were irradiated in the experimental breeder reactor II to a maximum fluence of ∼7 × 1022 neutrons/cm2 (E > 0.1 MeV) over a temperature range of 450 to 735°C. Tension tests were conducted at 232°C (fuel handling temperature), at the irradiation temperature, and at 110°C above the irradiation temperature to simulate transient reactor events. The alloy exhibited high strength and adequate ductility at 232°C. At the irradiation temperature, the strength remained high; however, a loss in ductility occurred with a trough in ductility occurring over a temperature range of 500 to 650°C. In tests simulating reactor transients, failures occurred with very low elongations (0 to 0.3 percent) over a test temperature range of 650 to 750°C.

No significant loss in grain boundary fracture stress was observed in the tests showing low ductility values. The loss in ductility can be explained by reduced differential between ultimate tensile strength and the yield stress.

Author Information

Bajaj, R
Westinghouse Advanced Reactors Division, Madison, Pa.
Shogan, RP
Westinghouse Research Laboratories, Pittsburg, Pa.
DeFlitch, C
Westinghouse Research Laboratories, Pittsburg, Pa.
Fish, RL
Hanford Engineering Development Laboratory, Westinghouse Hanford Co., Richland, Wash.
Paxton, MM
Hanford Engineering Development Laboratory, Westinghouse Hanford Co., Richland, Wash.
Bleiberg, ML
Westinghouse Advanced Reactors Division, Madison, Pa.
Price: $25.00
Contact Sales
Related
Reprints and Permissions
Reprints and copyright permissions can be requested through the
Copyright Clearance Center
Details
Developed by Committee: E10
Pages: 326–351
DOI: 10.1520/STP28222S
ISBN-EB: 978-0-8031-4794-2
ISBN-13: 978-0-8031-0755-7