In-Reactor Creep of Zr-2.5Nb Tubes at 570 K /

In-Reactor Creep of Zr-2.5Nb Tubes at 570 K /

Tubular specimens of Zr-2.5Nb, 23 mm internal diameter, have been creep tested in-reactor at 570 K. Specimens were biaxially stressed by internal pressure, with transverse stresses from 103 to 317 MPa. Two separate experiments are reported (a) U-501/2 which has specimens quenched from 1045 K; cold d...

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Bibliographic Details
Main Author: Ibrahim, EF (Author)
Corporate Authors: Zirconium in Nuclear Applications Portland, Ore., ASTM International, American Society for Testing and Materials
Format: Conference Proceeding Book
Language:English
Published: West Conshohocken, Pa. : ASTM International, 1974
Subjects:
Cold working
Creep strength
Internal pressure
Irradiation
Nuclear reactors > Materials
Tubes
Zirconium alloys
Zirconium

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