Investigation of Materials for a Water Cooled and Moderated Reactor [Declassified Version]

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Description

An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were established for all the materials under various conditions, such as irradiation, flow weld, stress, and various water conditions. Type-304 stainless steel was selected as the basic structural material. Operating conditions, … continued below

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Scheib, Louis August 1954.

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  • Main Title: Investigation of Materials for a Water Cooled and Moderated Reactor [Declassified Version]
  • Series Title: ORNL (Series)
  • Series Title: Oak Ridge National Laboratory Reports
  • Added Title: Oak Ridge National Laboratory Report ORNL-1915 (Del.)

Description

An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were established for all the materials under various conditions, such as irradiation, flow weld, stress, and various water conditions. Type-304 stainless steel was selected as the basic structural material. Operating conditions, to maintain minimum corrosion, were established also.

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  • Report No.: ORNL-1915 (Del.)
  • Accession or Local Control No: metadc1956994
  • Archival Resource Key: ark:/67531/metadc1956994

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Investigation of Materials for a Water Cooled and Moderated Reactor [Secret Version] (Report)

Investigation of Materials for a Water Cooled and Moderated Reactor [Secret Version]

An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were established for all the materials under various conditions, such as irradiation, flow, weld, stress, and various water conditions. Type-304 stainless steel was selected as the basic structural material. Operating conditions, to maintain minimum corrosion, were established also.

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Investigation of Materials for a Water Cooled and Moderated Reactor [Secret Version], ark:/67531/metadc1956995

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  • August 1954

Added to The UNT Digital Library

  • Feb. 6, 2022, 9:32 a.m.

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  • July 29, 2022, 1:03 a.m.

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Scheib, Louis. Investigation of Materials for a Water Cooled and Moderated Reactor [Declassified Version], report, August 1954; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc1956994/: accessed May 18, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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