The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

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Description

Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).

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20 p. : ill. ; 27 cm.

Creation Information

Pessl, H. J. July 30, 1963.

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  • Pessl, H. J. Metallurgy Research, Reactor and Fuels Laboratory, Hanford Laboratories

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Description

Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).

Physical Description

20 p. : ill. ; 27 cm.

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Technical Report Archive and Image Library

This selection of materials from the Technical Report Archive and Image Library (TRAIL) includes hard-to-find reports published by various government agencies. The technical publications contain reports, images, and technical descriptions of research performed for U.S. government agencies. Topics range from mining, desalination, and radiation to broader physics, biology, and chemistry studies. Some reports include maps, foldouts, blueprints, and other oversize materials.

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Creation Date

  • July 30, 1963

Added to The UNT Digital Library

  • Jan. 31, 2014, 11:57 a.m.

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Pessl, H. J. The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes, report, July 30, 1963; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc100631/: accessed July 21, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.