POSTIRRADIATION EXAMINATION OF 17-4 PH STAINLESS STEEL CONTROL ROD DRIVE RACK FROM SM-1 REACTOR

POSTIRRADIATION EXAMINATION OF 17-4 PH STAINLESS STEEL CONTROL ROD DRIVE RACK FROM SM-1 REACTOR [electronic resource]

A portion of the control rod drive system in the SM-1 Reactor, fabricated from l7-4 PH stainless steel, was examined at the Oak Ridge National Laboratory (ORNL) hot cells after successful operation in a pressurized-water environment for approximately three years. Examination included visual inspecti...

Full description

Saved in:
Bibliographic Details
Online Access: Online Access
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1961.
Subjects:
Configuration.
Control Elements.
Corrosion.
Failures.
Fluorescence.
Cracks.
Machine Parts.
Magnetic Materials.
Materials Testing.
Metallography.
Motors.
Power Plants.
Pressure.
Radiation Effects.
Radiation Protection.
Reactor Core.
Remote Handling.
Rods.
Servomechanisms.
Irradiation.
Sm-1.
Stainless Steels.
Stresses.
Water Coolant.
Reactor Technology.

Internet

Online Access

Online

Holdings details from Online
Call Number: E 1.99:ornl-3218
E 1.99:ornl-3218 Available

Similar Items