期刊文献+

球床式高温气冷堆MOX燃料循环优化 被引量:1

Optimization of MOX Fuel Cycles in Pebble Bed HTGR
下载PDF
导出
摘要 与压水堆相比,球床式高温气冷堆能在堆芯结构不做明显改变的情况下采用全堆芯装载混合氧化物(MOX)燃料元件。基于250MW球床模块式高温气冷堆堆芯结构,设计了4种球床式高温气冷堆下MOX燃料循环方式,包括铀钚混合的燃料球和独立的钚球与铀球混合装载的等效方式,采用高温气冷堆设计程序VSOP进行分析,比较了初装堆的有效增殖因数、燃料元件在堆芯内滞留时间、卸料燃耗、温度系数等主要物理特性。结果表明:采用纯铀和纯钚两种分离燃料球且铀燃料球循环时间更长的方案,平均卸料燃耗较高,总体性能较其他循环方式优越。 Compared with light water reactor(LWR),the pebble bed high temperature gas-cooled reactor(HTGR) is able to operate in a full mixed oxide(MOX) fuelled core without significant change to core structure design.Based on a reference design of 250 MW pebble bed HTGR,four MOX fuel cycles were designed and evaluated by VSOP program package,including the mixed Pu-U fuel pebbles and mixed loading of separate Pu-pebbles and U-pebbles.Some important physics features were investigated and compared for these four cycles,such as the effective multiplication factor of initial core,the pebble residence time,discharge burnup,and temperature coefficients.Preliminary results show that the overall performance of one case is superior to other equivalent MOX fuel cycles on condition that uranium fuel elements and plutonium fuel elements are separated as the different fuel pebbles and that the uranium fuel elements are irradiated longer in the core than the plutonium fuel elements,and the average discharge burnup of this case is also higher than others.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第3期427-431,共5页 Atomic Energy Science and Technology
基金 国家重大科技专项经费资助项目(ZX06901)
关键词 高温气冷堆 球床 MOX燃料 卸料燃耗 high temperature gas-cooled reactor pebble bed MOX fuel discharge burnup
  • 相关文献

参考文献5

  • 1FETTERMAN R J. AP1000 core design with 50% MOX loading[J]. Annals of Nuclear Ener- gy, 2009, 36(3): 324-330.
  • 2TRELLUE H R. Safety and neutronics: A com- parison of MOX vs UO2 fuel[J]. Progress in Nu- clear Energy, 2006, 48(2): 135-145.
  • 3WEI Jinfeng, SUN Yuliang, LI Fu. MOX fuel cycles in the HTGR reactor[C]//Proceedings of 3rd International Symposium on Symbiotic Nucle- ar Power System for 21st Century (ISSNP2010). Harbin, China: Harbin Engineering University, 2010.
  • 4李富,魏春琳,周旭华,等.模块式高温气冷堆的物理特性[C]//第十二届反应堆数值计算与粒子输运学术会议暨2008年反应堆物理会议论文集.合肥:中国科学院等离子体物理研究所,2008.
  • 5RUTTEN H J, HAAS K A, BROCKMANN H, et al. V. S. O. P. (99/05) computer code system for reactor physics and fuel cycle simula- tion [M]. Juelich, German: Juelich Research Center, 2005.

共引文献1

同被引文献16

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部