Localized Corrosion of Stainless Steels and High-Nickel Alloys in Simulated Superheat Reactor Environment

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Abstract. A program was instituted to study and reproduce the in-reactor intergranular failures of Type-304 stainless steel fuel cladding found in superheated steam. The program was directed toward finding ways to eliminate the cause of failure or to use improved alloys that would be less susceptible to failure. A materials screening test was developed in the out-of-pile superheat facilities with 1.5 ppm chloride added as sodium chloride to the recirculating water in the presence of typical boiling water reactor quantities of oxygen and hydrogen. During the test, the heater sheaths were exposed through several cycles to saturated steam (with its … continued below

Physical Description

68 pages ; illustrations.

Creation Information

Pearl, W. L.; Gaul, G. G. & Wozadlo, G. P. February 1964.

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  • Vallecitos Atomic Laboratory
    Publisher Info: General Electric Company. Vallecitos Atomic Laboratory. Atomic Power Equipment Department.
    Place of Publication: San Jose, California

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Description

Abstract. A program was instituted to study and reproduce the in-reactor intergranular failures of Type-304 stainless steel fuel cladding found in superheated steam. The program was directed toward finding ways to eliminate the cause of failure or to use improved alloys that would be less susceptible to failure. A materials screening test was developed in the out-of-pile superheat facilities with 1.5 ppm chloride added as sodium chloride to the recirculating water in the presence of typical boiling water reactor quantities of oxygen and hydrogen. During the test, the heater sheaths were exposed through several cycles to saturated steam (with its accompanying moisture carryover) and superheated steam. Failure of Type-304 stainless steel was obtained in periods of less than two weeks; the failures were predominantly transgranular. Type-347 and vacuum-melted Type-304 stainless steels failed in this NaCl-cycle test while Inconel-600, Incoloy-800, Hastelloy-X, Type-406 stainless steel, and vacuum-melted Type-310 stainless steel were acceptable. An improved chloride cycle test with 0.5 ppm chloride added as ferric chloride to the recirculating water was developed. An intergranular failure was obtained similar to that experienced in the superheat fuel cladding failures in the superheat in-pile loops in the Vallecitos Boiling-Water Reactor. Sensitized Type-304 and Type-316 stainless steels failed intergranularly in this test. Inconel-600, Incoloy-800, and vacuum-melted Type-310 stainless steel did not fail when exposed to the test for much longer time periods. During the development and performance of the cycle runs, the superheat facilities were exposed to a myriad of conditions within the extremes of the test parameters involved. Intergranular chemical attack was experienced essentially independent of stress, but the attack was generally distributed. In the presence of high stress, the intergranular attack was more localized and advanced normal to the stress. It is hypothesized that definite interplay exists between chemical attack and stress, and that the application of the stress increases the rate of the intergranular attack preferentially in a direction perpendicular to the stress.

Physical Description

68 pages ; illustrations.

Notes

Digitized from microopaque cards.

This work was part of the Superheat Program sponsored by the Atomic Energy Commission at the Atomic Power Equipment Department of the General Electric Company under Contract AT(04-3)-189 Project Agreement 13.

Includes bibliographic references (pages 42-43).

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  • Report No.: GEAP-4450
  • Grant Number: AT(04-3)-189 PA 13
  • SuDoc Number: Y 3.At 7:22/GEAP-4450
  • Accession or Local Control No: metadc1201410
  • Archival Resource Key: ark:/67531/metadc1201410

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Technical Report Archive and Image Library

The Technical Report Archive & Image Library (TRAIL) identifies, acquires, catalogs, digitizes and provides unrestricted access to U.S. government agency technical reports. The mission of TRAIL is to ensure preservation, discoverability, and persistent open access to government technical publications regardless of form or format.

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Imaged from microcard, these technical reports describe research performed for U.S. government agencies from the 1930s to the 1960s. The reports were provided by the Technical Report Archive and Image Library (TRAIL).

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Creation Date

  • February 1964

Added to The UNT Digital Library

  • Aug. 15, 2019, 10:26 p.m.

Description Last Updated

  • June 25, 2024, 1:22 a.m.

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Pearl, W. L.; Gaul, G. G. & Wozadlo, G. P. Localized Corrosion of Stainless Steels and High-Nickel Alloys in Simulated Superheat Reactor Environment, report, February 1964; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1201410/: accessed January 15, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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