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超临界六角形双排燃料组件性能分析

Performance Analysis on the Two-Row Hexagonal Fuel Assembly for Super Critical Water-Cooled Reactor
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摘要 利用物理-热工水力耦合计算程序系统(MCATHAS)分析2种六角形双排超临界燃料组件,充分考虑了超临界水冷堆(SCWR)中冷却剂、慢化剂轴向温度、密度的剧烈变化和功率分布的相互影响。计算结果表明,双排六角形组件具有均匀慢化和充分慢化性能,文中提出的D6-1型组件在仅采用一种燃料成分、不添加可燃毒物的情形下,其径向功率峰值因子低于1.10。另外,研究表明,由于组件间隙具有较大热周和较小流通面积,需要在实际工程应用中增加隔热涂层以降低组件外盒壁的导热率。 MCATHAS system, which is a code of coupled neutronics/thermal-hydraulics, is used for the calculating of the two two-row hexagonal fuel assemblies. Considering the mutual influence between the axial obvious evolution of density and temperature of the coolant and moderator and the relative power distribution, the results show the two-row hexagonal fuel assemblies keep the balance between uniform moderation and sufficient moderation. The radial power peaking factor of the D6-1 assembly in the paper is less than 1.10 under the condition of using the same enrichment fuel and without the burnable poison. In addition, due to the longer heated perimeter and the litter flow area of the assembly gap region, the conductivity of the assembly box needs to be smaller by adding some adiabatic material.
出处 《核动力工程》 EI CAS CSCD 北大核心 2013年第1期31-34,共4页 Nuclear Power Engineering
关键词 超临界水冷堆 燃料组件 双排六角形 物理热工耦合 Supercritical water cooled reactor, Fuel assembly, Two-row hexagonal, Coupled Neutronics/Thermal-hydraulics
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  • 1李满昌,王明利.超临界水冷堆开发现状与前景展望[J].核动力工程,2006,27(2):1-4. 被引量:19
  • 2Magnus MORI. Core Design Analysis of TheSupercr- itical Water Fast Reactor[D]. Stuttgart Universite ltalien, 2005.
  • 3Yamaji A, Oka Y. Three-Dimension Core Design of SCLWR-H with Neutronics and Thermal-Hydraulic Coupling[J]. Journal of Nuclear Science and Techno- logy, 2005,42(1): 8-19.
  • 4Waata C L. Coupled Neutronics/Thermal-Hydraulics Analysis of a High-Performance Light-Water Reactor Fuel Assembly[D]. Germany: Forschungszentrums Karlsruhe, Stuttgart University, 2005: 66-77.
  • 5Briesmeister J-F. MCNP-A General Monte Carlo N Particle Transport Code[M]. LA-13709-M, Version 4C. Los Alamos National Laboratory, March 2000.
  • 6Croft A G. A User's Manual for ORIGEN2 Computer Code [M]. ORNL/TM-7175. Oak Ridge National Laboratory. 1980.
  • 7Hofmeister J, Schulenberg T, Starflinger J. Optimisation of a Fuel Assembly for a HPLWR [C]. ICAPP, Seoul,Korea, 2005.
  • 8Waata C L.Coupled Neutronics/Thermal-Hydraulics Analysis of a High-Performance Light-Water Reactor Fuel Assembly[]..2006
  • 9Dobashi K,Oka Y,Koshizuka S.Core and Plant Designof the Power Reactor Cooled and Moderated by Supercritical Light Water with Single Tube Water Rods[].Annals of Nuclear Energy.1997
  • 10Briesmeister JF.MCNP-A General Monte Carlo Code for N-particle Transport Code[].LA--M.1997

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