Specific Zirconium Alloy Design Program Quarterly Progress Report: Seventh Quarter, October - December, 1963

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Description

Summary: All experimental work under the Corrosion Mechanism task has been completed. The remaining topical reports are being prepared by D. L. Douglass, now on assignment at Mol. Experimental work on the first round of 31 alloys and on the second round of 10 alloys has been completed. Steam exposures of at least 3000 hours were finished for all the alloys at all test temperatures, with exposures of some coupons to 6700 hours. Mathematical expression have been derived to describe all first round data for corrosion rates and hydriding rates at 300, 400, and 500 degrees C as a function … continued below

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iii, 50 pages ; illustrations.

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Klepfer, H. H.; Jaech, John L.; Blood, R. E.; Perrine, H. E. & Urata, M. E. January 1964.

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Description

Summary: All experimental work under the Corrosion Mechanism task has been completed. The remaining topical reports are being prepared by D. L. Douglass, now on assignment at Mol. Experimental work on the first round of 31 alloys and on the second round of 10 alloys has been completed. Steam exposures of at least 3000 hours were finished for all the alloys at all test temperatures, with exposures of some coupons to 6700 hours. Mathematical expression have been derived to describe all first round data for corrosion rates and hydriding rates at 300, 400, and 500 degrees C as a function of Nb, Cr, Fe, and Cu content. Solution of the equations for particular service temperatures yield Zr-Cr alloys at optimum at lower temperatures and Zr-Cu-Fe alloys as optimum at the higher temperatures. The second round test results show that neither Ni nor Be additions to Zr-Cr or Zr-Cu improve the performance over that of the optimum Zr-Cr or Zr-Cu-Fe alloys. For the first round heat treatment used, post-corrosion ductility depends on two factors in addition to alloy composition and hydrogen content: crystallographic texture and intermetallic aging reactions. Alloys with a high original ductility are embrittled less by a given amount of hydrogen than are alloys with low original ductility. From the second round tests, it was found that raising the final alpha annealing temperature from 565 to 788 degrees C gives better over-all corrosion, hydriding performance, and resistance to hydrogen embrittlement for both the Zr-Cr and Zr-Cu alloys tested.

Physical Description

iii, 50 pages ; illustrations.

Notes

Digitized from microopaque cards.

Prepared under U.S. Atomic Energy Commission Contract AT(04-3)-189 Project Agreement 24 for the Joint U.S.-Euratom Research and Development Program.

Includes bibliographic references (page 50).

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  • Report No.: GEAP-4484
  • Grant Number: AT(04-3)-189 PA 24
  • SuDoc Number: Y 3.At 7:22/GEAP-4484
  • Accession or Local Control No: metadc1201417
  • Archival Resource Key: ark:/67531/metadc1201417

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Technical Report Archive and Image Library

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  • January 1964

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  • Aug. 15, 2019, 10:26 p.m.

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  • June 25, 2020, 3:51 p.m.

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Klepfer, H. H.; Jaech, John L.; Blood, R. E.; Perrine, H. E. & Urata, M. E. Specific Zirconium Alloy Design Program Quarterly Progress Report: Seventh Quarter, October - December, 1963, report, January 1964; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1201417/: accessed May 30, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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