Property changes of G347A graphite due to neutron irradiation
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This article is published in Carbon.The article was published on 2016-11-01 and is currently open access. It has received 38 citations till now. The article focuses on the topics: Nuclear graphite & Neutron flux.read more
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Development of mesopores in superfine grain graphite neutron-irradiated at high fluence
Cristian I. Contescu,José David Arregui-Mena,Anne A. Campbell,Philip D. Edmondson,Nidia C. Gallego,Kentaro Takizawa,Yutai Katoh +6 more
TL;DR: In this paper, the unique ability of gas adsorption techniques to analyze open pores with sizes between sub-nanometer and sub-micron in bulk nuclear graphite with supporting microscopy results was demonstrated.
Journal ArticleDOI
A multi-technique experimental and modelling study of the porous structure of IG-110 and IG-430 nuclear graphite
TL;DR: In this paper, a multi-technique approach, consisting of pycnometry, low pressure gas adsorption and mercury porosimetry, is presented for nuclear graphite, which is validated for two nuclear-grade graphites designed for use in Generation IV nuclear reactors.
Journal ArticleDOI
A Review of Finite Element Method Models for Nuclear Graphite Applications
José David Arregui-Mena,Robert N. Worth,Graham Hall,Philip D. Edmondson,Alain B. Giorla,Timothy D. Burchell +5 more
TL;DR: A comprehensive overview of FEM methodologies is provided in this review, including: FEM software, basics steps to set up a FEM model, and analytical solutions used to validate simulations for this field of study.
Journal ArticleDOI
Surface morphology and microstructure evolution of IG-110 graphite after xenon ion irradiation and subsequent annealing
TL;DR: In this paper, IGS-110 graphite samples were polished and irradiated with Xe ions at various fluences, then annealed at high temperatures up to 1100°C.
References
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Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation
TL;DR: In this article, a theoretical model is presented to quantify the relative phonon-scattering effectiveness of the three dominant defect types produced by neutron irradiation: point defects, dislocation loops and voids.
Journal ArticleDOI
Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature
TL;DR: In this article, the use of thermal expansion from continuous dilatometry to calculate the SiC irradiation temperature is presented, which is an automated process requiring minimal setup time and is compared to an electrical resistivity and isochronal annealing investigation.
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