摘要
建立了典型的快堆六角形栅元堆芯模型,研究了多种类型的燃料在快中子能谱辐照环境下经过较长时间辐照后的性能,对不同燃料堆芯在运行寿期末的乏燃料组成成分进行了分析。结果表明,在栅元结构完全一样且初始剩余反应性基本相同的情况下,燃料反应性损失从小到大的顺序是:金属燃料<氮化物燃料<碳化物燃料<氧化物燃料;在整个寿期中,使用Pu驱动的燃料比使用235U驱动的燃料反应性下降得慢;金属燃料寿期末乏燃料中按初始装载燃料质量平均后的超铀核素的质量最小,其他依次为氧化物<氮化物<碳化物;由于初始装载量的增多,使用Pu驱动的燃料寿期末乏燃料超铀核素的总量比使用235U驱动的燃料多,同时,乏燃料Pu中的易裂变同位素的份额比235U驱动燃料的少。从中子学角度考虑,UZr燃料是比较理想的长寿命快堆堆芯燃料类型。
By using a typical fast reactor core model formed by hexagonal lattice cell, this paper studied the perfo.rmance of different types of nuclear fuels, which are loaded respectively as fuel in this fast reactor core model for a long time operation, and analyzed the spent fuel compositions of different fuel types at EOL. The results indicated that, in the case of same lattice cell and similar initial reactivity, the burnup reactivity loss of metallic fuel is the smallest, followed by nitride fuel, carbide fuel and finally oxide fuel, while within same chemical form, fuels driven by Pu provide smaller reactivity loss compared to fuels driven by 235U. Analysis of spent fuel composition shows that metallic fuel also exhibits smallest TRUs mass （averaged by initial fuel mass） of spent fuel, and then followed by oxide fuel, nitride fuel and carbide fuel, while at the same time, compared to fuels driven by 235U, Pu based fuels were found to discharge more TRUs mass because of the increase of initial Pu loading mass, and thus lower percent of fissile materials in spent fuel. In terms of neutronics UZr fuel is an ideal fuel for long life fast reactor core.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2008年第1期53-56,共4页
Nuclear Power Engineering
关键词
长寿命
快堆
燃耗反应性损失
乏燃料
成分
Long life, Fast reactor, Burnup reactivity loss, Spent Fuel, Composition
