Radiation effects on the microstructure of a 9Cr-ODS alloy

Jian Gan, T. R. Allen, R. C. Birtcher, S. Shutthanandan, S. Thevuthasan

Research output: Contribution to journalArticle

7 Citations (Scopus)

Abstract

Oxide dispersion strengthened (ODS) steels are prime candidates for high-temperature, high-dose cladding in advanced nuclear reactors. When a 9Cr-ODS alloy was irradiated with 5 MeV nickel ions at temperatures of 500-700°C to doses up to 150 dpa, there was no significant change in the dislocation arrangement. For oxide particles, there is a small shrinkage in size and increase in density with increasing irradiation dose. This work confirms that oxide particles and the microstructure of the 9Cr-ODS show minimal changes under irradiation at temperatures up to 700°C and doses up to 150 dpa.

Original languageEnglish
Pages (from-to)24-28
Number of pages5
JournalJOM
Volume60
Issue number1
DOIs
Publication statusPublished - Jan 2008
Externally publishedYes

Fingerprint

Radiation effects
Oxides
microstructure
oxide
Microstructure
Dosimetry
irradiation
Irradiation
Steel
Nuclear reactors
Nickel
dislocation
Temperature
nickel
steel
temperature
radiation effect
Ions
dose
ion

ASJC Scopus subject areas

  • Geochemistry and Petrology
  • Geotechnical Engineering and Engineering Geology
  • Materials Science(all)
  • Metals and Alloys

Cite this

Gan, J., Allen, T. R., Birtcher, R. C., Shutthanandan, S., & Thevuthasan, S. (2008). Radiation effects on the microstructure of a 9Cr-ODS alloy. JOM, 60(1), 24-28. https://doi.org/10.1007/s11837-008-0003-5

Radiation effects on the microstructure of a 9Cr-ODS alloy. / Gan, Jian; Allen, T. R.; Birtcher, R. C.; Shutthanandan, S.; Thevuthasan, S.

In: JOM, Vol. 60, No. 1, 01.2008, p. 24-28.

Research output: Contribution to journalArticle

Gan, J, Allen, TR, Birtcher, RC, Shutthanandan, S & Thevuthasan, S 2008, 'Radiation effects on the microstructure of a 9Cr-ODS alloy', JOM, vol. 60, no. 1, pp. 24-28. https://doi.org/10.1007/s11837-008-0003-5
Gan J, Allen TR, Birtcher RC, Shutthanandan S, Thevuthasan S. Radiation effects on the microstructure of a 9Cr-ODS alloy. JOM. 2008 Jan;60(1):24-28. https://doi.org/10.1007/s11837-008-0003-5
Gan, Jian ; Allen, T. R. ; Birtcher, R. C. ; Shutthanandan, S. ; Thevuthasan, S. / Radiation effects on the microstructure of a 9Cr-ODS alloy. In: JOM. 2008 ; Vol. 60, No. 1. pp. 24-28.
@article{9c560d3fad07497e8987c605412a6e6d,
title = "Radiation effects on the microstructure of a 9Cr-ODS alloy",
abstract = "Oxide dispersion strengthened (ODS) steels are prime candidates for high-temperature, high-dose cladding in advanced nuclear reactors. When a 9Cr-ODS alloy was irradiated with 5 MeV nickel ions at temperatures of 500-700°C to doses up to 150 dpa, there was no significant change in the dislocation arrangement. For oxide particles, there is a small shrinkage in size and increase in density with increasing irradiation dose. This work confirms that oxide particles and the microstructure of the 9Cr-ODS show minimal changes under irradiation at temperatures up to 700°C and doses up to 150 dpa.",
author = "Jian Gan and Allen, {T. R.} and Birtcher, {R. C.} and S. Shutthanandan and S. Thevuthasan",
year = "2008",
month = "1",
doi = "10.1007/s11837-008-0003-5",
language = "English",
volume = "60",
pages = "24--28",
journal = "JOM",
issn = "1047-4838",
publisher = "Minerals, Metals and Materials Society",
number = "1",

}

TY - JOUR

T1 - Radiation effects on the microstructure of a 9Cr-ODS alloy

AU - Gan, Jian

AU - Allen, T. R.

AU - Birtcher, R. C.

AU - Shutthanandan, S.

AU - Thevuthasan, S.

PY - 2008/1

Y1 - 2008/1

N2 - Oxide dispersion strengthened (ODS) steels are prime candidates for high-temperature, high-dose cladding in advanced nuclear reactors. When a 9Cr-ODS alloy was irradiated with 5 MeV nickel ions at temperatures of 500-700°C to doses up to 150 dpa, there was no significant change in the dislocation arrangement. For oxide particles, there is a small shrinkage in size and increase in density with increasing irradiation dose. This work confirms that oxide particles and the microstructure of the 9Cr-ODS show minimal changes under irradiation at temperatures up to 700°C and doses up to 150 dpa.

AB - Oxide dispersion strengthened (ODS) steels are prime candidates for high-temperature, high-dose cladding in advanced nuclear reactors. When a 9Cr-ODS alloy was irradiated with 5 MeV nickel ions at temperatures of 500-700°C to doses up to 150 dpa, there was no significant change in the dislocation arrangement. For oxide particles, there is a small shrinkage in size and increase in density with increasing irradiation dose. This work confirms that oxide particles and the microstructure of the 9Cr-ODS show minimal changes under irradiation at temperatures up to 700°C and doses up to 150 dpa.

UR - http://www.scopus.com/inward/record.url?scp=46949091103&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=46949091103&partnerID=8YFLogxK

U2 - 10.1007/s11837-008-0003-5

DO - 10.1007/s11837-008-0003-5

M3 - Article

VL - 60

SP - 24

EP - 28

JO - JOM

JF - JOM

SN - 1047-4838

IS - 1

ER -