Preparation of binderless nanopore-isotropic graphite for inhibiting the liquid fluoride salt and Xe135 penetration for molten salt nuclear reactor

Song, Jinliang; Zhao, Yanling; Zhang, Junpeng; He, Xiujie; Zhang, Baoliang; Lian, Pengfei; Liu, Zhanjun; Zhang, Dongsheng; He, Zhoutong; Gao, Lina; Xia, Hao; Zhou, Xingtai; Huai, Ping; Guo, Quangui; Liü, Lang

doi:10.1016/j.carbon.2014.07.022

Cited by 44 publications

(15 citation statements)

References 27 publications

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“…This raw material is able to be compacted and to become strongly bonded via 'sintering' in the absence of a binder. The MCMB-based graphite shows high strength, fine microstructure, and a marked inhibition of liquid fluoride-salt infiltration [9]. Due to their completely spherical shape, MCMB particles spontaneously stack in random orientation upon compaction, thereby forming an isotropic texture in spite of the anisotropic nature of MCMB itself.…”

Section: Introductionmentioning

confidence: 99%

Homogenous and highly isotropic graphite produced from mesocarbon microbeads

Shen

Huang

Shen

et al. 2015

Carbon

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Section: Introductionmentioning

confidence: 99%

Homogenous and highly isotropic graphite produced from mesocarbon microbeads

Shen

Huang

Shen

et al. 2015

Carbon

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“…Henceforth this eutectic composition is denoted FLiNaK salt. The melting point of FLiNaK salt is measured precisely by Differential Scanning Calorimetry (DSC) technique and estimated to be 454.0 ± 0.2 o C. The C/C composite samples and solid FLiNaK salt were introduced into a high-pressure reactor 49 as shown in Fig. 5 .…”

Section: Methodsmentioning

confidence: 99%

High temperature in-situ synchrotron-based XRD study on the crystal structure evolution of C/C composite impregnated by FLiNaK molten salt

Feng

Yang

et al. 2017

Sci Rep

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An in-situ real-time synchrotron-based grazing incidence X-ray diffraction was systematically used to investigate the crystal structural evolution of carbon fiber reinforced carbon matrix (C/C) composite impregnated with FLiNaK molten salt during the heat-treatment process. It was found that the crystallographic thermal expansion and contraction rate of interlayer spacing d 002 in C/C composite with FLiNaK salt impregnation is smaller than that in the virgin sample, indicating the suppression on interlayer spacing from FLiNaK salt impregnated. Meanwhile the crystallite size L C002 of C/C composite with FLiNaK salt impregnation is larger than the virgin one after whole heat treatment process, indicating that FLiNaK salt impregnation could facilitate the crystallization of C/C composite after heat treatment process. This improved crystallization in C/C composite with FLiNaK salt impregnation suggests the synthetic action of the salt squeeze effect on crooked carbon layer and the release of internal residual stress after heating-cooling process. Thus, the present study not only contribute to reveal the interaction mechanism between C/C composite and FLiNaK salt in high temperature environment, but also promote the design of safer and more reliable C/C composite materials for the next generation molten salt reactor.

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“…The IG-110 graphite is not t for MSR for the pores are generally larger than 1 mm, which could lead to molten salt impregnation and gas diffusion. 9 The surface morphology of PyC is pretty uniform and dense, which consists of ne grains with the size about 0.5-3 mm, and it is the typical characteristics of pyrolytic carbon growth cone appearance. SEM micrographs show few aws or cracks on the surface of the coatings and it has good sealing effect to protect the nuclear graphite against the permeation of molten uoride salts and the diffusion of ssion gases.…”

Section: Morphology Changesmentioning

confidence: 98%

“…Nuclear graphite is widely used as a moderator, reector and core supporting structure in nuclear reactors, however, in the molten salt nuclear reactor (MSR), one of the six Generation IV reactors, traditional nuclear graphite faces a molten salt impregnation problem. [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15] Studies at the Oak Ridge National Laboratory have shown that if the pore size of graphite is greater than 1 micron, the molten salt will penetrate into the graphite and produce local high temperatures quickly damaging the graphite. 5 In addition, ssion product gases (mainly 135 Xebased) affect the performance of graphite as a moderator, so the pores of graphite must also be kept below 100 nm to prevent ssion products from diffusing into the graphite.…”

Section: Introductionmentioning

confidence: 99%

“…Compact PyC was prepared by uidized bed or xed bed technology and adopted as a long-term development program using methane as precursor at a high temperature of 1800 C and low pressure of $270 Pa in a vacuum induction furnace. 3,[9][10][11][16][17][18] Although PyC meets the MSR requirements for graphite pore size, the relevant data related to its irradiation is not available, and it is not certain whether PyC can tolerate the irradiation environment in the reactor. Therefore, it is necessary to prove whether PyC can be used as a candidate for suitable nuclear graphite in MSR.…”

Section: Introductionmentioning

confidence: 99%

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Direct characterization of ion implanted nanopore pyrolytic graphite coatings for molten salt nuclear reactors

et al. 2018

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Nanopore pyrolytic graphite coatings (PyC, average pore size $64 nm) were prepared on graphite to inhibit liquid fluoride salt and Xe 135 penetration. The samples were irradiated with 7 MeV Xe 26+ to a total peak dose of 0.1, 0.5, 2.5 and 5.0 displacements per atom at room temperature to study the irradiation resistance of the PyC. The effect of irradiation on the properties of the graphite was evaluated. With the increase of irradiation dose, the surface morphology of the coatings tends to be smoother. At the total peak dose of 2.5 dpa, peeling and spalling on the surface of the samples have been identified, indicating the surface microstructure of the graphite has been damaged by Xe 26+ bombardment. Raman results indicated the increase in the degree of disorder and decrease of in-plane crystallite size with the irradiation dose, and the new PyC was more sensitive to irradiation than IG-110 graphite. The nanohardness at peak dose increased with the irradiation dose, but decreased at 2.5 dpa. The results of a hardness test also show PyC has a higher irradiation sensitivity. Fig. 5 TEM micrographs of (a) unirradiated PyC cross section between PyC and IG-110, (b) bright-field, (c) dark field, (d) selected area of electron diffraction, (e) HRTEM image of surface, (f) HRTEM image near cross section and (g) dark field TEM of interface region at high magnification, (h) bright-field TEM of interface region at high magnification.This journal is

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Preparation of binderless nanopore-isotropic graphite for inhibiting the liquid fluoride salt and Xe135 penetration for molten salt nuclear reactor

Cited by 44 publications

References 27 publications

Homogenous and highly isotropic graphite produced from mesocarbon microbeads

Homogenous and highly isotropic graphite produced from mesocarbon microbeads

High temperature in-situ synchrotron-based XRD study on the crystal structure evolution of C/C composite impregnated by FLiNaK molten salt

Direct characterization of ion implanted nanopore pyrolytic graphite coatings for molten salt nuclear reactors

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