期刊文献+

惰性基质燃料元件Doppler系数分析 被引量:1

Analysis on Doppler Coefficient of Inert Matrix Fuel
下载PDF
导出
摘要 本文采用中子输运程序MCNP,基于ENDF/B-Ⅶ.1核数据库,对几种典型惰性基质燃料(IMF)的Doppler系数进行了计算,并通过理论分析给出了各核素对Doppler系数贡献的表达式。结果表明:在相同惰性基质条件下,武器级Pu燃料的Doppler系数的绝对值小于反应堆级Pu燃料的;在惰性基质中添加232 Th可使Doppler系数更负,且可使IMF获得与低浓UO2燃料相近的Doppler系数;硼可燃毒物对Doppler系数的贡献为正效应,而铒可燃毒物则可进一步增强负Doppler系数,有利于反应堆的固有安全性。 Based on neutron transport code MCNP and ENDF/B-Ⅶ.1 database ,Doppler coefficients of typical inert matrix fuel (IMF) were calculated and expressions of isotopic contributions to Doppler coefficient were given by theoretical analysis . The results indicate that absolute Doppler coefficient of weapon-grade plutonium IMF is smaller than that of reactor-grade plutonium fuel . The additive of 232 Th makes the Doppler coefficient more negative which is similar to UO2 in quantity .The contribution of boron burnable poison to Doppler coefficient is positive ,however ,erbium burnable poison can further enhance the negative Doppler coefficient ,w hich is conducive to reactor inherent safety .
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2014年第6期1067-1071,共5页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(91126018) 湖南省教育厅科学研究项目资助(11A101)
关键词 惰性基质燃料 Doppler系数 蒙特卡罗模拟 inert matrix fuel Doppler coefficient Monte-Carlo simulation
  • 相关文献

参考文献10

  • 1CHAUVIN N, KONINGS R J M, MATZKE H. Optimisation of inert matrix fuel concepts for americium transmutation[J]. Journal of Nuclear Materials, 1999, 274: 105-111.
  • 2BARANAEV Y D, POPOV V V, SHARAPOV V N, et al. The feasibility of employing inert matrix ceramic fuels in a Russian light water re- actor[J]. Journal of Nuclear Materials, 2003, 319: 154-158.
  • 3CALABRESE R, VETTRAINO F, TVER- BERG T. Comparative study of inert matrix fuels concepts from IFA-652 experiment[C]//ICONE17- 75151. Brussels, Belgium: [s. n.], 2009.
  • 4CARMACK W, FIELDING R, HAMILTON H B, et al. AECL/US INERI-development of inert matrix fuels for plutonium and minor actinide management in power reactors-fuel requirements and down-select report, INL/EXT-05-00436 [R]. USA: Idaho National Laboratory, 2005.
  • 5MEDVEDEV P G, FRANK S M, O' HOLLE- RAN T P, et al. Dual phase MgO-ZrOz ceramics for use in LWR inert matrix fuel[J]. Journal of Nuclear Materials, 2005, 342: 48-62.
  • 6RONCHI C, OTTAVIANI J P, DEGUELDRE C, et al. Thermophysical properties of inert ma- trix fuels for actinide transmutation[J]. Journal of Nuclear Materials, 2003, 320: 54-65.
  • 7PARATTE J M, CHAWLA R, AKIE H, et al.A numerical neutronics benchmark study for inert matrix plutonium fuels in uranium dioxide and mixed plutonium-uranium dioxide environments [J]. Progress in Nuclear Energy, 2001, 38: 335- 342.
  • 8PARATTE J M, AKIE H, CHAWLA R, et al. Comparisons of cell calculations for uranium-free light water reactor fuels[J]. Nuclear Technolo- gy, 2000, 130: 159-176.
  • 9Viability of inert matrix fuel in reducing plutoni- um amounts in reactors, IAEA-TECDOC-1516 [R]. Vienna: IAEA, 2006.
  • 10THILAGAM L, SUNNY C S, SUBBAIAH K V. Doppler coefficient of reactivity-benchmark calculations for different enrichments of UO2 [C] //Joint International Topical Meeting on Mathe- matics & Computation and Supercomputing in Nuclear Applications (M&C+SNA 2007). Cali- fornia: [s. n.], 2007.

同被引文献8

引证文献1

二级引证文献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