Sealing nuclear graphite with pyrolytic carbon

Feng, Song; Xu, Li; Li, Li; Yang, Xinmei; Zhou, Xingtai

doi:10.1016/j.jnucmat.2013.06.035

Cited by 27 publications

(6 citation statements)

References 30 publications

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“…Bernardet et al 11) coated glassy carbon and pyrolytic carbon on a graphite substrate and found that pyrolytic carbon was more effective than glassy carbon in the protection of a graphite substrate against a molten salt attack. The effectiveness of using pyrolytic carbon to seal graphite from molten salts was also reported in the studies of Feng et al 12) , He et al 19) and Song et al 20) The comparison in terms of sealing effectiveness against molten salts between pyrolytic carbon and the graphite foil used in the present study needs further assessment. Fig.…”

Section: Resultssupporting

confidence: 70%

“…In MSR, molten salt ows between the reactor core and the heat exchanger serve as both fuel and coolant. Due to its chemical inertness, ability to slow down fast neutrons and good irradiation resistance, graphite has been proposed as a candidate for exposure to molten salts as a moderator channel [8][9][10][11][12][13] . Graphite is generally resistant to chemical attack by uoride salts 8,9) ; nevertheless, nuclear grade graphite generally demonstrates relatively low mechanical strength and a relatively high level of porosity 11,12) .…”

Section: The Corrosion Behavior Of a Variety Of Ceramics In Lif-mentioning

confidence: 99%

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Graphite Foil-Incorporated PAN/Pitch/Phenolic-Derived Carbon/Carbon Composite and Preliminary Hermetic Sealing Test in Molten Fluoride Salt

et al. 2017

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Section: Resultssupporting

confidence: 70%

Section: The Corrosion Behavior Of a Variety Of Ceramics In Lif-mentioning

confidence: 99%

Graphite Foil-Incorporated PAN/Pitch/Phenolic-Derived Carbon/Carbon Composite and Preliminary Hermetic Sealing Test in Molten Fluoride Salt

et al. 2017

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“…This layer has a high degree of planar orientation and substantially reduces infiltration of molten salt and gases in graphite but requires careful engineering to avoid the potential for separation because graphite and PyC have different rates of dimensional changes during irradiation. 43 The PyC coating is expected to substantially reduce the structural damage that might be caused by the known tendency of Li ϩ and F Ϫ ion intercalation of between graphite layers. 44 However, such layers may also slow tritium kinetics of absorption.…”

Section: Tritium Control and Carbonmentioning

confidence: 99%

Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward

et al. 2017

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Three advanced nuclear power systems use liquid salt coolants that generate tritium and thus face the common challenges of containing and capturing tritium to prevent its release to the environment. The fluoride salt-cooled high-temperature reactor (FHR) uses clean fluoride salt coolants and the same graphite-matrix coated-particle fuel as high-temperature gas-cooled reactors. Molten salt reactors (MSRs) dissolve the fuel in a fluoride or chloride salt with release of fission product tritium into the salt. In most FHR and MSR systems, the baseline salts contain lithium where isotopically separated 7 Li is proposed to minimize tritium production from neutron interactions with the salt. The Chinese Academy of Sciences plans to start operation of a 2-MW(thermal) molten salt test reactor by 2020. For high-magnetic-field fusion machines, the use of lithium enriched in 6 Li is proposed to maximize tritium generation-the fuel for a fusion machine. Advances in superconductors that enable higher power densities may require the use of molten lithium salts for fusion blankets and as coolants. Recent technical advances in these three reactor classes have resulted in increased government and private interest and the beginning of a coordinated effort to address the tritium control challenges in 700°C liquid salt systems. We describe characteristics of salt-cooled fission and fusion machines, the basis for growing interest in these technologies, tritium generation in molten salts, the environment for tritium capture, models for high-temperature tritium transport in salt systems, alternative strategies for tritium control, and ongoing experimental work. Several methods to control tritium appear viable. Limited experimental data are the primary constraint for designing efficient cost-effective methods of tritium control.

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“…In the first category, graphite impregnation with hydrocarbons (e.g., pitch, furans) or resin precursors (e.g., polyfurfuryl alcohol, phenolic resins) has led to a generally acceptable impregnation procedure with pitch; this procedure was used to fabricate the CGB graphite bars used in the MSRE. 15 More graphite development studies published in recent years reported impregnation experiments with phenolic resin 16 and surface sealing by pyrolytic carbon, 15,17,18,19 glassy carbon, 20 silicon carbide, 21,22 or combinations thereof. 23 Early attempts within the MSRE program to obtain compact graphite bodies by manipulating the grain size and nature of raw materials 15 belong to the second category.…”

Section: Introductionmentioning

confidence: 99%