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nsuf-18-1596

NSUF 18-1596: Micro-structural investigation of the pore structure of uncrept and crept irradiated PCEA graphite specimens with SEM and FIB tomography

Graphite has been proposed as a moderator material for the Very High Temperature Reactor (VHTR) reactors designs. The lifetime of VHTR depends on the extent of changes produced...

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    • The data at this site comes from research conducted through the U. S. Department of Energy’s (DOE) Nuclear Science User Facilities (NSUF) program. The data provided at this site is for information only and is not provided for any particular purpose or use. Neither the U. S. Government nor any agency thereof (including DOE), Battelle Energy Alliance, LLC (BEA), nor any other entity makes any warranties, representations, or guarantees, express or implied, regarding the data provided at this site, including, without limitation, that the data is fit or safe for any use or purpose or that its use would not infringe privately owned rights. Neither the U. S. Government nor any agency thereof (including DOE), BEA, nor any other entity associated with DOE’s NSUF program assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any data on this site. Reference herein, if any, to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not constitute or imply its endorsement, recommendation, or favor by the U. S. Government or any agency thereof (including DOE), BEA, or any other entity.

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