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Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
Zhao He,Jinliang Song,Pengfei Lian,Dongqing Zhang,Zhanjun Liu 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.5
SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (ToyoTanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor(MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon compositecoating, respectively. Both structure and property of modified graphite were carefully researched andcontrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensiveproperties such as more compact structure and higher resistance to molten salt infiltration. With theprotection of coatings, the infiltration amounts of fluoride salt into modified graphite were much lessthan that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride saltinto IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2,and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR.
Zhang, Heyao,He, Zhao,Song, Jinliang,Liu, Zhanjun,Tang, Zhongfeng,Liu, Min,Wang, Yong,Liu, Xiangdong Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.6
Irradiation-induced damage of binderless nanoporous-isotropic graphite (NPIG) prepared by isostatic pressing of mesophase carbon microspheres for molten salt reactor was investigated by 3.0 MeV He<sup>+</sup> irradiation at room temperature and high temperature of 600 ℃, and IG-110 was used as the comparation. SEM, TEM, X-ray diffraction and Raman spectrum are used to characterize the irradiation effect and the influence of temperature on graphite radiation damage. After irradiation at room temperature, the surface morphology is rougher, the increase of defect clusters makes atom flour bend, the layer spacing increases, and the catalytic graphitization phenomenon of NPIG is observed. However, the density of defects in high temperature environment decreases and other changes are not obvious. Mechanical properties also change due to changes in defects. In addition, SEM and Raman spectra of the cross section show that cracks appear in the depth range of the maximum irradiation dose, and the defect density increases with the increase of irradiation dose.
Zhao He,Hongchao Zhao,Jinliang Song,Xiaohui Guo,Zhanjun Liu,Yajuan Zhong,T. James Marrow 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.4
Green pitch coke with an average particle size of 2 mm was adopted as densifier and added to the rawmaterials of conventional A3-3 matrix graphite (MG) to prepare modified A3-3 matrix graphite (MMG)by the quasi-isostatic molding method. The structure, mechanical and thermal properties were assessed. Compared with MG, MMG had a more compact structure, and exhibited improved properties of highermechanical strength, higher thermal conductivity and better molten salt barrier performance. Notably,under the same infiltration pressure of 5 atm, the fluoride salt occupation of MMG was only 0.26 wt%,whereas it was 15.82 wt% for MG. The densification effect of green pitch coke endowed MMG withimproved properties for potential use in the spherical fuel elements of molten salt reactor.
Failure behaviors of C/C composite tube under lateral compression loading
Yantao Gao,Yuexia Guan,Ke Li,Min Liu,Can Zhang,Jinliang Song 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.7
Mechanical responses and failure behaviors of advanced C/C composite tube are very important for structural component design in nuclear reactor. In this study, an experimental investigation was conducted to study mechanical properties of C/C composite tube. Quasi-static compression loading was applied to a type of advanced composite tube to determine the response of the quasi-static load displacement curve during progressive damage. Acoustic emissions (AE) signals were captured and analyzed to characterize the crack formation and crack development. In addition, the crack propagation of the specimens was monitored by imaging technique and failure mode of the specimen was analyzed. FEM is appled to simulate the stress distribution. Results show that advanced C/C composite tube exhibits considerable energy absorption capability and stability in load-carrying capacity.