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Microstructure evolution in ZrC irradiated with Kr ions

  • Jian Gan
  • , Mitchell K. Meyer
  • , Robert C. Birtcher
  • , Todd R. Allen

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

2 Scopus citations

Abstract

The gas-cooled fast reactor (GFR) is one of six concepts for the Generation-IV nuclear energy system. The fuel for the GFR requires both a high heavy metal loading and the ability to withstand temperatures up to 1600°C during a loss of coolant accident. ZrC is among the few potential refractory ceramic materials with necessary properties to be considered as matrix materials for a dispersed carbide fuel. The radiation response of ZrC to high dose and temperature is a critical research need. This work investigated the microstructure of ZrC irradiated with 1 MeV Kr ions to doses of 10 and 30 dpa at 27°C and 10 and 70 dpa at 800°C with a damage rate approximately 3.0 ×10-3 dpa/s. No radiation-induced amor-phization was found. A lattice expansion of approximately 7 % was observed for ZrC irradiated to 70 dpa at 800°C.

Original languageEnglish
Title of host publicationEffects of Radiation on Materials
Subtitle of host publication22nd Symposium
PublisherAmerican Society for Testing and Materials
Pages358-364
Number of pages7
ISBN (Print)0803134010, 9780803134010
StatePublished - 2006
Event22nd Symposium on Effects of Radiation on Materials - Boston, MA, United States
Duration: Jun 8 2004Jun 10 2004

Publication series

NameASTM Special Technical Publication
Volume1475 STP
ISSN (Print)0066-0558

Conference

Conference22nd Symposium on Effects of Radiation on Materials
Country/TerritoryUnited States
CityBoston, MA
Period06/8/0406/10/04

Keywords

  • Dislocation
  • Irradiation
  • Kr ions
  • Lattice expansion
  • Microstructure
  • ZRC

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