期刊文献+

基于TRISO燃料的小型压水堆研究 被引量:1

Studies on the Small Pressurized Water Reactor Based on TRISO Fuels
下载PDF
导出
摘要 目前世界上运行的大部分压水堆都采用二氧化铀(UO2)作为核燃料,锆合金作为包壳.该技术虽然成熟,但在高温下仍存在一定缺陷.新开发的TRISO(Tristructural-isotropic)燃料可以长时间在1 600℃的温度下保持燃料和包壳的完整性,防止裂变产物释放到环境中,在压水堆中使用TRISO燃料替代常规UO2芯块燃料可以大大提高反应堆的安全性.本研究使用TRISO包覆颗粒燃料的小型压水堆,对不同富集度组件排列下的有效增殖系数、堆芯换料周期、中子通量分布等进行分析讨论,并比较2种燃料棒在反应堆正常运行环境下的温度分布.计算结果表明,从换料周期、通量展平、燃料的中心最高温度这3个方面看,在小型压水堆中采用TRISO燃料棒替代常规UO2燃料棒是可行的,使用TRISO燃料的堆芯具有更优异的安全性. At present,most of pressurized water reactors (PWR) use UO2 fuel pellets as nuclear fuels in the world. Although fuel pellets are utilized widely,they suffer from some defects under high temperature. The newly developed tristructural-isotropic(TRI- SO) fuel can maintain the integrity of the fuel and cladding,which is able to prevent the fission products from being released to the environment at a temperature of 1 600 ~C for a long time. Therefore,the safety of the reactor can be significantly improved by using TRISO fuel instead of the conventional UO~ pellet fuel in PWR. In this paper, a small pressurized water reactor using TRISO fuel was considered. The effective multiplication factor under different uranium enrichment, the refuel cycle, and the neutron flux distribution were discussed. The temperature distributions for two kinds of fuel rods in the reactor were compared. Calculation results show that, according to the fuel reloading length, flux flatted, and temperature distribution, using TRISO instead of conventional UO2 fuel rods is feasible and safer in the small pressurized water reactor.
出处 《厦门大学学报(自然科学版)》 CAS CSCD 北大核心 2015年第5期603-607,共5页 Journal of Xiamen University:Natural Science
基金 厦门大学校长基金(2012121034 20720150095)
关键词 TRISO燃料 小型压水堆 安全性 TRISO fuel small pressurized water reactor safety
  • 相关文献

参考文献25

  • 1李廷伍.二氧化铀陶瓷芯块设计的改进[J].核动力工程,1986(5):49-52.
  • 2Kortov V, Ustyantsev Y. Chernobyl accident : causes, con- sequences and problems of radiation measurements[J]. Radiation Measurements, 2013,55 : 12-16.
  • 3Saenko V,Ivanov V. The Chernobyl accident and its con sequences[J]. Clinical Oncology, 2011,23 : 234-243.
  • 4Evangeliou N, Balkanski Y, Cozic A, et al. Global and lo- cal cancer risks after the Fukushima nuclear power plant accident as seen from Chernobyl:a modeling study for ra- diocaesium (^134 Cs & ^137 Cs) [J]. Environment Internation al, 2014,64 : 17-27.
  • 5Povinec P P, Gera M, Holar K, et al. Dispersion of Fuku- shima radionuclides in the global atmosphere and the o- cean[J]. Applied Radiation and Isotopes, 2013, 81: 383-392.
  • 6Rahu K. Site-specific cancer risk in the Baltic cohort of Chernobyl cleanup workers, 1986- 2007 [J]. European Journal of Cancer, 2013,49 : 2926-2933.
  • 7Pratama M A, Yoneda M, Yosuke A Y, et al. Modeling migration of Cs-137 in sewer system of fukushima city u- sing model for radionuclide migration in urban environ- ment and drainage system (MUD)[J]. International Jour- nal of Engineering and Technology, 2014 (6) : 402-408.
  • 8Steinhauser G, Brandl A, Johnson T E. Comparison of the Chernobyl and Fukushima nuclear accidents:a review of the environmental impacts[J]. Science of The Total Envi- ronment, 2014,470 : 800-817.
  • 9徐世江,康飞宇.核工程中的炭和石墨材料[M].北京:清华大学出版社,2010.
  • 10Price M S T. The dragon project origins, achievements and legacies[J]. Nuclear Engineering and Design, 2012,251:60-68.

二级参考文献7

  • 1朱钧国,杨冰,张秉忠,黄锦涛,徐世江.高温气冷堆包覆燃料颗粒的化学气相沉积[J].清华大学学报(自然科学版),1996,36(11):65-71. 被引量:11
  • 2Porta J, Pinto PL, Bonnet M,et al. Coated Particle Fuel to Improve Safety, Design, Economics in Water-Cooled and Gas-Cooled Reactors [J].Progr Nucl Energy, 2001,38(3-4):407~410.
  • 3Kauchi M, Shimazu Y.Optimal Burnable Poison-Loading in a PWR With Carbon Coated Particle Fuel [J].J Nucl Sci Technol,2003,40(1):22~29.
  • 4Bernard B, Dominique G, Frank C, et al. Utilization/disposition of Reactor-Grade Plutonium in High-Temperature Gas-Cooled Reactors [J]. Nuclear Technology,2004,145(3):266~274.
  • 5Kloosterman JL, Golovko VV, van Dam H, et al. Conceptual Design of a Fluidized Bed Nuclear Reactor [J].Nucl Sci Eng, 2001,139:118~137.
  • 6ElGenk, Mohamed S, Tournier, et al. An Analysis of Coated Particles Fuel Compact-General Purpose Heat Source (CPFC-GPHS)[J]. Progr Nucl Energy, 2004, 44(3):215~236.
  • 7朱钧国,杨冰,张秉忠,邵友林,黄国礼,梁彤翔,彭新立,周寅甲.10MW高温气冷堆包覆燃料颗粒的研制[J].核动力工程,2002,23(2):76-81. 被引量:8

共引文献4

同被引文献1

引证文献1

二级引证文献3

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