In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel

J. Hawthorne; L. Steele

doi:10.1520/STP43539S

SYMPOSIA PAPER Published: 01 January 1965

STP43539S

In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel

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This paper describes an experimental irradiation assembly and associated instrumentation which has been developed and successfully utilized for the performance of dynamic, in-reactor low cycle fatigue tests of reactor pressure vessel steels. The equipment provides for the simultaneous reverse bend testing of as many as 15 sheet-type specimens representing a range of strain amplitudes at controlled temperatures in the range of 300 to 700 F.

The results of an exploratory investigation on the fatigue resistance of ASTM A302-B steel during irradiation at 500 F are presented and compared with data from out-of-reactor control tests.

Author Information

Hawthorne, J., R.

U. S. Naval Research Laboratory, Washington, D. C.

Steele, L., E.

U. S. Naval Research Laboratory, Washington, D. C.

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Details

Developed by Committee: E10

Pages: 350–363

DOI: 10.1520/STP43539S

ISBN-EB: 978-0-8031-6007-1

ISBN-13: 978-0-8031-6161-0

In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel

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