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8.59×10^(20)cm^(-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。
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.
出处
《原子能科学技术》
EI
CAS
CSCD
2003年第z1期50-52,69,共4页
Atomic Energy Science and Technology
关键词
高温气冷堆
球形燃料元件
辐照考验
high temperature gas-cooled reactor
spherical fuel element
irradiation testing
