Investigation of Cracked Lithium Hydride Reactor Vessels

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Description

Visual examination of lithium hydride reactor vessels revealed cracks that were adjacent to welds, most of which were circumferentially located in the bottom portion of the vessels. Sections were cut from the vessels containing these cracks and examined by use of the metallograph, scanning electron microscope, and microprobe to determine the cause of cracking. Most of the cracks originated on the outer surface just outside the weld fusion line in the base material and propagated along grain boundaries. Crack depths of those examined sections ranged from {approximately}300 to 500 {micro}m. Other cracks were reported to have reached a maximum depth ... continued below

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25 pages

Creation Information

bird, e.l. & mustaleski, t.m. June 1, 1999.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

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  • Oak Ridge Y-12 Plant
    Publisher Info: Oak Ridge Y-12 Plant, TN (United States)
    Place of Publication: Tennessee

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Description

Visual examination of lithium hydride reactor vessels revealed cracks that were adjacent to welds, most of which were circumferentially located in the bottom portion of the vessels. Sections were cut from the vessels containing these cracks and examined by use of the metallograph, scanning electron microscope, and microprobe to determine the cause of cracking. Most of the cracks originated on the outer surface just outside the weld fusion line in the base material and propagated along grain boundaries. Crack depths of those examined sections ranged from {approximately}300 to 500 {micro}m. Other cracks were reported to have reached a maximum depth of 1/8 in. The primary cause of cracking was the creation of high tensile stresses associated with the differences in the coefficients of thermal expansion between the filler metal and the base metal during operation of the vessel in a thermally cyclic environment. This failure mechanism could be described as creep-type fatigue, whereby crack propagation may have been aided by the presence of brittle chromium carbides along the grain boundaries, which indicates a slightly sensitized microstructure.

Physical Description

25 pages

Source

  • Other Information: PBD: 1 Jun 1999

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  • Report No.: Y/DV-1614
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/11014 | External Link
  • Office of Scientific & Technical Information Report Number: 11014
  • Archival Resource Key: ark:/67531/metadc627527

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  • June 1, 1999

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • May 6, 2016, 1:31 p.m.

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bird, e.l. & mustaleski, t.m. Investigation of Cracked Lithium Hydride Reactor Vessels, report, June 1, 1999; Tennessee. (digital.library.unt.edu/ark:/67531/metadc627527/: accessed September 26, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.