NSUF 19-1773: BET and TEM characterization of nuclear graphite irradiated at temperatures below 230°C

Graphite is the moderator material of some Generation IV reactors concepts and British Advanced Gas-cooled Reactors (AGR). Failure of multiple graphite components is considered to be one of the limiting factors for plant life of the AGR and some Generation IV designs. Part of the assessment performance predictions of Generation IV graphite bricks are based on simulations that require information of the volumetric lattice changes in single graphite crystals. TEM data at temperatures below 300˚C is currently unavailable limiting the understanding of graphitic material defects at the conditions that may be found in carbon-based materials in Generation IV reactors designs. The authors propose to implement Brunauer-Emmett-Teller (BET) and Transmission Electron Microscopy (TEM) analysis to determine the effects of irradiation under low temperature conditions. The study of samples irradiated at low temperatures would also improve the fundamental understanding of the defect mobility and evolution in the graphite.

Additional Info

Field Value
Awarded Institution Canadian Nuclear Laboratories
Embargo End Date 2026-02-27
Facility Tech Lead Kory Linton
NSUF Call FY 2019 RTE 2nd Call
PI Wenjing Li
PIE Facilities Low Activation Materials Design and Analysis Laboratory
Project Member Dr. Philip Edmondson - University of Manchester (https://orcid.org/0000-0001-8990-0870)
Project Member Dr. Jose Arregui-Mena - Oak Ridge National Laboratory (https://orcid.org/0000-0002-6131-3268)
Project Member Cristian Contescu, Distinguished Staff Scientist - Oak Ridge National Laboratory (https://orcid.org/0000-0002-7450-3722)
Project Member Dr. wenjing li, Research Scientist - Canadian Nuclear Laboratories
Project Notes Awarded on 05/14/2019
Project Type RTE
Publication Multiscale characterization and comparison of historical and modern nuclear graphite grades Jose Arregui-Mena Materials Characterization 190 None
RTE Number 1773