Inherent damage tolerance of fine grained nuclear graphite at elevated temperatures

DOI

Current UK reactors use a graphite composite material in the core and this material comprises coarse grains and about 20 vol.% porosity. This material functions well so far but the 14 UK reactors are reaching the end of their designed lifetime. Plans for next generation of nuclear power plants are therefore underway, and new designs of this graphite composite have come up online. The new materials have finer grains and therefore are stronger. However, compared with the coarse grained UK graphite, the new material may be more 'brittle'. This is what we are trying to find out in this experiment. Neutrons will tell us how much the lattice has deformed in the material under load; we then take digital images of the surface of the sample to calculate the overall deformation. By comparing the two, the amount of 'non-brittleness' of the material at different temperatures can be derived.

Identifier
DOI https://doi.org/10.5286/ISIS.E.90880556
Metadata Access https://icatisis.esc.rl.ac.uk/oaipmh/request?verb=GetRecord&metadataPrefix=oai_datacite&identifier=oai:icatisis.esc.rl.ac.uk:inv/90880556
Provenance
Creator Dr Saurabh Kabra; Dr Houzheng Wu; Dr Dong Liu; Mr Zhizhen Shao; Mr Daniel Bradshaw
Publisher ISIS Neutron and Muon Source
Publication Year 2021
Rights CC-BY Attribution 4.0 International; https://creativecommons.org/licenses/by/4.0/
OpenAccess true
Contact isisdata(at)stfc.ac.uk
Representation
Resource Type Dataset
Discipline Construction Engineering and Architecture; Engineering; Engineering Sciences
Temporal Coverage Begin 2018-03-06T09:00:00Z
Temporal Coverage End 2018-03-14T09:16:00Z