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燃料束
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  “燃料束”译为未确定词的双语例句
     The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical method.
     用有限元法编制了三维二群中子扩散堆芯燃料管理程序,给出中子通量分布、功率分布、燃料束的比燃耗分布,有效增殖系数,吸收棒、点火棒和水位的效应,管道温升和管道流量以及其它关心的物理量。
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  相似匹配句对
     Fuel cells
     燃料电池
短句来源
     Fuel Cell
     燃料电池
短句来源
     Research and Design on Fuel Bundle of Advanced Heavy Water Reactor
     先进重水反应堆燃料物理研究与设计
短句来源
     FLOW FIELD MEASUREMENTS USING LDA AND NUMERICAL COMPUTATION FOR ROD BUNDLE OF REACTOR FUEL ASSEMBLY
     反应堆燃料组件棒流场的激光测试和计算
短句来源
     Beam Chopper
     流调制器
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In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical...

In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical method. Choosing arbitary triangular prizm elements and quatraanqular prizm elements to simulate reactor core. Automatical mesh formation and manual mesh formation are jointly adopted. This code has both automatic refuelling capability and manual refuelling capability. In order to extend its application, the conversion of irradiated core into another specific core and recalculation functions are provided to simulate reactor core operation and in core fuel management. The adopted Techebyshev acceleration convergency method make the calculation precise and rapid.

重水动力堆的装换料是在带功率下进行的、相邻管道换料方向相反的双向连续换料。用有限元法编制了三维二群中子扩散堆芯燃料管理程序,给出中子通量分布、功率分布、燃料束的比燃耗分布,有效增殖系数,吸收棒、点火棒和水位的效应,管道温升和管道流量以及其它关心的物理量。使用任意三棱柱元素和四棱柱元素,较真实地模拟反应堆边界。网格的剖分采用自动和人工相结合。程序既有自动装换料的功能,又有人工装换料的功能;为了使它有广泛的适应性,还特别设置了从辐照过的堆芯转变为另一种特定堆芯,并重新开始计算的功能。它可综合模拟堆芯运行和燃料管理。采用源迭代和切比雪夫加速收敛技巧使程序精度高,运算速度快。用3D-IAEA和3DPHWR对程序进行了考核,达到了预期的效果。

In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical...

In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical method. Choosing arbitary triangular prizm elements and quatraanqular prizm elements to simulate reactor core. Automatical mesh formation and manual mesh formation are jointly adopted. This code has both automatic refuelling capability and manual refuelling capability. In order to extend its application, the conversion of irradiated core into another specific core and recalculation functions are provided to simulate reactor core operation and in core fuel management. The adopted Techebyshev acceleration convergency method make the calculation precise and rapid.

重水动力堆的装换料是在带功率下进行的、相邻管道换料方向相反的双向连续换料。用有限元法编制了三维二群中子扩散堆芯燃料管理程序,给出中子通量分布、功率分布、燃料束的比燃耗分布,有效增殖系数,吸收棒、点火棒和水位的效应,管道温升和管道流量以及其它关心的物理量。使用任意三棱柱元素和四棱柱元素,较真实地模拟反应堆边界。网格的剖分采用自动和人工相结合。程序既有自动装换料的功能,又有人工装换料的功能;为了使它有广泛的适应性,还特别设置了从辐照过的堆芯转变为另一种特定堆芯,并重新开始计算的功能。它可综合模拟堆芯运行和燃料管理。采用源迭代和切比雪夫加速收敛技巧使程序精度高,运算速度快。用3D-IAEA和3DPHWR对程序进行了考核,达到了预期的效果。

 
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