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高温堆燃料元件研制

Research and Development of HTR Fuel Element

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【作者】 徐世江徐志昌杨冰左开芬邱学良唐春和

【Author】 Xu Shijiang;Xu Zhichang;Yang Bing;Zuo Kaifen;Qiu Xueliang;Tang Chunhe;Institute of Nuclear Energy Technology,Tsinghua University;

【机构】 清华大学核能技术设计研究院

【摘要】 为中国10MW高温试验模块堆研制了球形燃料元件,它由包覆燃料颗粒弥散在石墨基体里的燃料区和由不含燃料的同样基体材料外壳组成,燃料区和无燃料区之间没有物理上的分界面。改进了燃料核芯的溶胶凝胶制备工艺,使之兼有内、外凝胶工艺的优点;包覆燃料颗粒采用TRISO结构,实验室产品的冷态性能与国际同类产品的相当,初步辐照结果良好;用化学提纯工艺制出了核纯天然石墨粉;用准等静压的方法制造球形燃料元件,性能指标达到了设计要求;建立并发展出高温堆燃料研究和发展所需的常规的及非常规的性能测试方法,满足了实验研究的需要。

【Abstract】 Spherical fuel element is chosen for 10MW HTR test module, which will be built in China. Themodule is composed of a fuel zone with the diameter of 50ram and a fuel-free shell with the thickness of5mm. The fuel zone is made of coated fuel particle of TRISO type and graphite matrix, the shell made ofthe same material as the matrix of the fuel zone. A modified external gelation process is used for producingthe fuel kernel of the coated fuel particle. With this method, the fabrication process is improved. Coatedfuel particle with preirradiation properties comparable to those as described in some literatare is produced.Preliminary irradiation experiment is done on the coated fuel particle with positive results. Nuclear purenatural flake graphite is obtained by chemical purification process. Spherical fuel element with theproperties meeting the design standards is fabricated. Normal and special qualification methods are set up forthe research and development of HTR fuel element.

【基金】 863计划资助课题
  • 【文献出处】 高技术通讯 ,High Technology Letters , 编辑部邮箱 ,1992年07期
  • 【分类号】TL352
  • 【下载频次】43
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