摘要
锆铀合金通过氢化可制得U-ZrH_x燃料。合金中加入0.2—0.4wt%碳,有效地防止了燃料棒氢化过程中出现开裂的现象。氢化系统采用常压、高温、小流量的通氢方式,分级保温保压慢速冷却的氢化工艺及调整最终的氢化温度和压力,能够控制U-ZrH_x燃料的氢锆原子比H/Zr,以满足使用要求。
The Zr-U alloy can be changed into U-ZrH_x fuel through hydriding.when 0.2—0.4wt% carbon is added in the alloy, cracking of alloy rods can bc° protected effectily during hydriding. Using lower hydrogen pressure, higher hydriding temperature, little hydrogen fluence, slow cooling by step and adjusting final hydriding temperature and pressure in system, the H/Zr of U-ZrH_x fuel can be controled to satisfy requirement of use.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1991年第1期58-62,共5页
Nuclear Power Engineering
关键词
脉冲堆
锆-铀合金
氢化
均匀性
Pulsed reactor, Zr-U alloy, Hydriding, Homogeneity,Atom ratio of hydrogen to zirconium.