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JOURNAL OF NUCLEAR MATERIALS · 2014 · IF 2.016

SiC coating: An alternative for the protection of nuclear graphite from liquid fluoride salt

Xiujie He,Jinliang Song,Jie Tan,Baoliang Zhang,Huihao Xia,Zhoutong He,Xingtai Zhou,Mingwen Zhao,Xiangdong Liu,Li Xu,Shuo Bai

SiC coating is produced on a nuclear graphite (NG) substrate using chemical vapor deposition at 1150 °C to protect it from molten salt diffusion . Infiltration studies, performed in molten FLiNaK salt under an argon atmosphere at 5 atm, show that uncoated NG exhibits significantly higher weight gain than SiC-coated NG. The continuous and compact SiC coating exhibits excellent infiltration resistance in liquid fluoride salt as confirmed by synchrotron radiation X-ray microbeam fluorescence.

CAS / MDL: 7789-24-4 7681-49-4

研究领域: 材料科学 · 核能工程

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JOURNAL OF NUCLEAR MATERIALS · 2013 · IF 1.211

Protection of nuclear graphite toward liquid fluoride salt by isotropic pyrolytic carbon coating

Xiujie He,Jinliang Song,Li Xu,Jie Tan,Huihao Xia,Baoliang Zhang,Zhoutong He,Lina Gao,Xingtai Zhou,Mingwen Zhao,Zhiyong Zhu,Shuo Bai

Infiltration studies were performed on uncoated nuclear graphite and isotropic pyrolytic carbon (PyC) coated graphite in molten FLiNaK salt at 650 °C under argon atmosphere at 1, 3 and 5 atm. Uncoated graphite shows weight gain more obviously than that of PyC coated graphite. Nuclear graphite with PyC coating exhibits excellent infiltration resistance in molten salt due to the small open porosity as conformed from scanning electron microscopy and mercury injection experiments.