SYMPOSIA PAPER Published: 01 January 2006

Microstructure Evolution in ZrC Irradiated with Kr ions


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.

Author Information

Gan, J
Idaho National Laboratory, Idaho Falls, ID, 83415-6000
Meyer, MK
Idaho National Laboratory, Idaho Falls, ID, 83415-6000
Birtcher, RC
Argonne National Laboratory, Argonne, IL
Allen, TR
The University of Wisconsin, Madison, WI
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Developed by Committee: E10
Pages: 358–364
DOI: 10.1520/STP37591S
ISBN-EB: 978-0-8031-5518-3
ISBN-13: 978-0-8031-3401-0