ISSN: 1546-962X
Page Count: 7
Microstructure Evolution in ZrC Irradiated with Kr ions
Gan, J
Research Scientist,
Idaho National Laboratory,
ID
Meyer, MK
Physicist,
Argonne National Laboratory,
IL
Birtcher, RC
Professor,
The University of Wisconsin,
WI
Allen, TR
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 amorphization was found. A lattice expansion of approximately 7 % was observed for ZrC irradiated to 70 dpa at 800°C.
Keywords:
ZrC, Kr ions, microstructure, irradiation, dislocation, lattice expansion
Paper ID: JAI12376
DOI: 10.1520/JAI12376
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Title Microstructure Evolution in ZrC Irradiated with Kr ions
Symposium Effects of Radiation on Materials: 22nd International Symposium, 2004-06-10
Committee E10