Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957

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Description

A second test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel has been completed. The joint and bellows have now received 104 thermal cycles and 148 mechanical deflections. The joint and bellows have functioned properly; corrosion damage has been negligible, except for a small area on the bellows which has undergone pitting attack. Long-term runs with uranyl sulfate solutions of the concentration proposed or use in the HRT have shown the solution to be stable at 300 C. Substituting heavy water for normal water caused no difference in either corrosion … continued below

Physical Description

48 pages : illustrations

Creation Information

Griess, J. C. F.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al. January 31, 1957.

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  • Main Title: Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957
  • Series Title: CF (Series)
  • Series Title: Oak Ridge National Laboratory Reports
  • Added Title: Oak Ridge National Laboratory Report CF-57-1-144

Description

A second test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel has been completed. The joint and bellows have now received 104 thermal cycles and 148 mechanical deflections. The joint and bellows have functioned properly; corrosion damage has been negligible, except for a small area on the bellows which has undergone pitting attack. Long-term runs with uranyl sulfate solutions of the concentration proposed or use in the HRT have shown the solution to be stable at 300 C. Substituting heavy water for normal water caused no difference in either corrosion or solution stability. Experiments in which chromic acid was used to pretreat stainless steel have shown that, under certain conditions, the pretreated film can exist in uranyl sulfate solutions at flow rates in excess of the critical velocity for relatively long periods of time. The practicability of using titanium inserts in high turbulent areas of stainless steel loops to minimize corrosion has been demonstrated. The corrosiveness of beryllium sulfate solutions containing dissolved uranium trioxide has been determined at 250 and 280 C. Laboratory studies with regard to stress-corrosion cracking have shown that high stressed type 347 stainless steel will crack in boiling uranyl sulfate solutions containing 25 and 50 ppm chloride ions.

Physical Description

48 pages : illustrations

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Digitized from microopaque cards (2).

Includes bibliographic references (pages 47-48).

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  • Report No.: CF-57-1-144
  • Grant Number: W-7405-eng-26
  • SuDoc Number: Y 3.At 7:22/CF-57-1-144
  • Accession or Local Control No: metadc1202842
  • Archival Resource Key: ark:/67531/metadc1202842

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  • January 31, 1957

Added to The UNT Digital Library

  • July 9, 2023, 5:29 p.m.

Description Last Updated

  • April 10, 2024, 9:14 a.m.

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Griess, J. C. F.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al. Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957, report, January 31, 1957; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1202842/: accessed January 16, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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