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10MW高温气冷堆燃料元件的辐照考验
Irradiation Testing of the Fuel Element for 10 MW High Temperature Gas-cooled Reactor
【摘要】 10MW高温气冷堆燃料元件的辐照考验在俄罗斯IVV-2M堆内进行,辐照考验于2000年7月13日开始,现仍在进行中。至2002年6月14日,燃料元件最高燃耗(以金属铀计,全文同)已达77000MW·d/t,累积快中子注量达8.59×1020cm-2。本文描述辐照样品的冷态性能、辐照装置、辐照条件和已获得的辐照考验结果。
【Abstract】 The irradiation testing of the fuel element for 10 MW high temperature gas-cooled reactor(HTR-10) in Tsinghua University is being carried out in the Russian IVV-2M research reactor. This testing started on July 13,2000. Up to June 14,2002, the maximum burnup and fast neutron fluence reached 77 000 MW · d/t and 8. 59× 1020/cm2 , respectively. The paper describes the performance of the irradiation samples, irradiation equipment, irradiation condition and the irradation results obtained already.
【关键词】 高温气冷堆;
球形燃料元件;
辐照考验;
【Key words】 high temperature gas-cooled reactor; spherical fuel element; irradiation testing;
【Key words】 high temperature gas-cooled reactor; spherical fuel element; irradiation testing;
- 【文献出处】 原子能科学技术 ,Atomic Energy Science and Technology , 编辑部邮箱 ,2003年S1期
- 【分类号】TL424;TL352
- 【被引频次】3
- 【下载频次】184