摘要
反应堆中堆芯传热问题非常复杂.本文对压水堆燃料元件棒内的传热做了简化,将燃料芯块视为含内热源的稳态传热,芯块与包壳之间的间隙以及包壳看作稳态导热,探讨燃料元件棒内热量的传递,得到各区间的温度分布、热流量分布.
Heat transfer of reactor core is a very complex question in a reactor.Through simplifying heat transfer of the PWR fuel element rod,regarding as steady-state heat transfer of internal heat source in the fuel element rod,as steady-state heat conduction in cladding and in clearance between pellets and cladding,this paper has discussed heat transfer in the fuel element rod,and obtained the distribution of temperature and heat flux in every region.
出处
《咸宁学院学报》
2010年第6期5-7,共3页
Journal of Xianning University
关键词
核能
传热
压水堆
燃料元件棒
Nuclear Energy
Heat Transfer
Pressurized-Water Reactor(PWR)
Fuel Element Rod
Cladding