...aphite-moderated reactor 改进型气冷石墨慢化反应堆 gas-cooled graphite-moderated high-temperature reactor 石墨高温气冷堆 graphite moderated pile 石墨反应堆 ..
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讨论了高温气冷堆元件球后处理首端过程用固定床燃烧法去除石墨的可行性。
The feasibility of removing graphite by fixed bed burning technology in the headend process of HTGR graphite ball-element reprocessing is discussed.
石墨广泛地用做核反应堆慢化材料、反射层材料和堆芯结构材料，在高温气冷堆中还用来做燃料元件。
In nuclear reactors, graphite is used widely as moderators, reflectors, constructive materials of reactor core and fuel elements in high temperature gas cooled reactors.
在10 MW高温气冷堆(HTR - 10)中，由于石墨构件的磨损会产生石墨粉尘，将影响反应堆的正常运行。
In 10mw High Temperature Gas-cooled reactor (HTR-10), the wear of graphite components generates the graphite dust to influence the normal working of the reactor.
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