Phase Transformations in Neutron-Irradiated Zircaloys-Reference-Cited by-同舟云学术

Phase Transformations in Neutron-Irradiated Zircaloys

Published:1987-01-01 Issue: Volume: Page:676-699
ISSN:
Container-title:Radiation-Induced Changes in Microstructure: 13th International Symposium (Part I)
language:en
Short-container-title:

Author:

Chung HM¹

Affiliation:

1. Argonne National Laboratory, Material Science and Technology Division 1 Metallurgist , , 9700 S. Cass Ave., Argonne, IL60439 .

Abstract

Microstructural evolution in Zircaloy-2 and -4 spent-fuel cladding specimens after three years of irradiation in commercial power reactors has been investigated by transmission and high-voltage electron microscopies. Two kinds of precipitates induced by the fastneutron irradiation in the reactors have been identified, that is, Zr3O and cubic-ZrO2 particles approximately 2 to 10 nm in size. By means of specimen tilting and dark-field stereomicroscopy, the bulk nature of the cubic-ZrO2 particles has been shown. The Zr(Fex,Cr1−x)2 and Zr2(Fex,Ni1−x) intermetallic precipitates normally present in the as-fabricated material virtually dissolved in the spent-fuel cladding specimens after a fast-neutron fluence of ∼4 × 1021 n/cm2 in the power reactors. The observed radiation-induced phase transformations are discussed in relation with the currently available understanding of the alloy characteristics.

Publisher

ASTM International100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959

Link

https://dl.astm.org/stps/book/chapter-pdf/35884/10_1520_stp33851s.pdf

Reference29 articles.

1. Zirconium in the Nuclear Industry: Seventh International Symposium, STP 939, American Society for Testing and Materials, Philadelphia, 1987.

2. Cheng, B., Adamson, R. B., Bell, W. L., and Proebstle, R. A., Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Myrtle Beach, SC, 22–25 Aug. 1983, p. 274.

3. Chung, H. M., Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Monterey, CA, 9–12 Sept. 1985, pp. 153-159.

4. Williams, C. D. and Ells, C. E., Philosophical Magazine 1478-6435, Vol. 18, 1968, p. 763.

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