Segregation of tin in Zircaloy-2 under proton irradiation

Arthur Thompson Motta, Clement Lemaignan, Donald R. Olander

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

Simulating neutron irradiation with charged particles would allow materials to be tested for possible deleterious irradiation effects before being used in reactors. The higher damage rates from charged particle irradiation as compared to neutron irradiation make it possible to achieve comparable doses in significantly smaller times. In this study, tin precipitates between 0.1 and 0.5 μm in diameter were observed at the surface of Zircaloy-2 thin foils after 5.5-MeV proton irradiation. The samples were irradiated to a dose of 1 dpa, at a temperature of 360 K, and a dose rate of 10-4 dpa·s-1. X-ray analysis showed the precipitates to be almost pure tin, which was confirmed by diffraction analysis that showed the particles to be β-tin. A simple model was developed that explains the observations by a preferential solute-interstitial interaction, leading to a defect-induced solute flux to the surface, with consequent precipitation from supersaturated solid solution. The calculation of the solute-interstitial interaction is based on an equilibrium between the two types of interstitials, solute and solvent. The interstitials are created in stoichiometric proportions and then allowed to convert from one type to the other with a difference of δ in the energy barriers for the two conversions. Applying the model to the observations with δ = 0.1 eV yields between two and five monolayers of solute segregated to the surface during the irradiation time.

Original languageEnglish (US)
Title of host publicationASTM Special Technical Publication
PublisherPubl by ASTM
Pages689-702
Number of pages14
Edition1125
ISBN (Print)080311477X
StatePublished - Dec 1 1992
Event15th International Symposium on Effects of Radiation on Materials - Nashville, TN, USA
Duration: Jun 19 1990Jun 21 1990

Publication series

NameASTM Special Technical Publication
Number1125
ISSN (Print)0066-0558

Other

Other15th International Symposium on Effects of Radiation on Materials
CityNashville, TN, USA
Period6/19/906/21/90

Fingerprint

Proton irradiation
Tin
Neutron irradiation
Irradiation
Charged particles
Precipitates
Energy barriers
X ray analysis
Metal foil
Dosimetry
Solid solutions
Monolayers
Diffraction
Fluxes
Defects
Temperature

All Science Journal Classification (ASJC) codes

  • Engineering(all)

Cite this

Motta, A. T., Lemaignan, C., & Olander, D. R. (1992). Segregation of tin in Zircaloy-2 under proton irradiation. In ASTM Special Technical Publication (1125 ed., pp. 689-702). (ASTM Special Technical Publication; No. 1125). Publ by ASTM.
Motta, Arthur Thompson ; Lemaignan, Clement ; Olander, Donald R. / Segregation of tin in Zircaloy-2 under proton irradiation. ASTM Special Technical Publication. 1125. ed. Publ by ASTM, 1992. pp. 689-702 (ASTM Special Technical Publication; 1125).
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Motta, AT, Lemaignan, C & Olander, DR 1992, Segregation of tin in Zircaloy-2 under proton irradiation. in ASTM Special Technical Publication. 1125 edn, ASTM Special Technical Publication, no. 1125, Publ by ASTM, pp. 689-702, 15th International Symposium on Effects of Radiation on Materials, Nashville, TN, USA, 6/19/90.

Segregation of tin in Zircaloy-2 under proton irradiation. / Motta, Arthur Thompson; Lemaignan, Clement; Olander, Donald R.

ASTM Special Technical Publication. 1125. ed. Publ by ASTM, 1992. p. 689-702 (ASTM Special Technical Publication; No. 1125).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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T1 - Segregation of tin in Zircaloy-2 under proton irradiation

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N2 - Simulating neutron irradiation with charged particles would allow materials to be tested for possible deleterious irradiation effects before being used in reactors. The higher damage rates from charged particle irradiation as compared to neutron irradiation make it possible to achieve comparable doses in significantly smaller times. In this study, tin precipitates between 0.1 and 0.5 μm in diameter were observed at the surface of Zircaloy-2 thin foils after 5.5-MeV proton irradiation. The samples were irradiated to a dose of 1 dpa, at a temperature of 360 K, and a dose rate of 10-4 dpa·s-1. X-ray analysis showed the precipitates to be almost pure tin, which was confirmed by diffraction analysis that showed the particles to be β-tin. A simple model was developed that explains the observations by a preferential solute-interstitial interaction, leading to a defect-induced solute flux to the surface, with consequent precipitation from supersaturated solid solution. The calculation of the solute-interstitial interaction is based on an equilibrium between the two types of interstitials, solute and solvent. The interstitials are created in stoichiometric proportions and then allowed to convert from one type to the other with a difference of δ in the energy barriers for the two conversions. Applying the model to the observations with δ = 0.1 eV yields between two and five monolayers of solute segregated to the surface during the irradiation time.

AB - Simulating neutron irradiation with charged particles would allow materials to be tested for possible deleterious irradiation effects before being used in reactors. The higher damage rates from charged particle irradiation as compared to neutron irradiation make it possible to achieve comparable doses in significantly smaller times. In this study, tin precipitates between 0.1 and 0.5 μm in diameter were observed at the surface of Zircaloy-2 thin foils after 5.5-MeV proton irradiation. The samples were irradiated to a dose of 1 dpa, at a temperature of 360 K, and a dose rate of 10-4 dpa·s-1. X-ray analysis showed the precipitates to be almost pure tin, which was confirmed by diffraction analysis that showed the particles to be β-tin. A simple model was developed that explains the observations by a preferential solute-interstitial interaction, leading to a defect-induced solute flux to the surface, with consequent precipitation from supersaturated solid solution. The calculation of the solute-interstitial interaction is based on an equilibrium between the two types of interstitials, solute and solvent. The interstitials are created in stoichiometric proportions and then allowed to convert from one type to the other with a difference of δ in the energy barriers for the two conversions. Applying the model to the observations with δ = 0.1 eV yields between two and five monolayers of solute segregated to the surface during the irradiation time.

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Motta AT, Lemaignan C, Olander DR. Segregation of tin in Zircaloy-2 under proton irradiation. In ASTM Special Technical Publication. 1125 ed. Publ by ASTM. 1992. p. 689-702. (ASTM Special Technical Publication; 1125).