SYMPOSIA PAPER Published: 01 January 1963
STP41758S

Radiation Effects in Reactor Structural Materials

Source

The effect of fast neutron radiation on the impact strength of two precipitation hardening stainless steels has been determined using full-size Charpy V-notch specimens. The brittle-ductile impact transition temperature of type 17-4 PH stainless steel aged at 1100 F was found to increase from approximately room temperature to values above 300 F after irradiation at 545 F to exposures in excess of 5 x 1019 neutrons per sq cm > 1 Mev. The impact strength of doubly aged austenitic type A-286 stainless steel was found to increase from about 30 ft-lb in the unirradiated condition to approximately 50 ft-lb after irradiation.

A technique for performing in-reactor slow-cycle fixed range fatigue tests on thin-walled tubing is described. Results of preliminary work on type 304 stainless steel tubing are presented. Irradiation in a core position in the General Electric Test Reactor during tests was found to produce a threefold decrease in strain cycle life of type 304 stainless steel in a configuration similar to that of fuel element cladding.

Author Information

Reynolds, Myron, B.
General Electric Co., Pleasanton, Calif.
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: 311–324
DOI: 10.1520/STP41758S
ISBN-EB: 978-0-8031-5984-6
ISBN-13: 978-0-8031-6138-2