首页> 外文会议>International conference on nuclear engineering;ICONE5 >CAN A DOUBLE BEAM MODEL OF FUEL ASSEMBLIES IMPROVE EVALUATIONS OF THE SEISMIC BEHAVIOR OF A PWR CORE ?
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CAN A DOUBLE BEAM MODEL OF FUEL ASSEMBLIES IMPROVE EVALUATIONS OF THE SEISMIC BEHAVIOR OF A PWR CORE ?

机译:燃料组件的双梁模型能否改善压水堆芯地震行为的评价?

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Analysis of the seismic behavior of a standard core of arnPressurized Water Reactor aims primarily to evaluate thernintegrity of the mixing grids and of the fuel rods.rnFor the purpose of such a mechanical analysis, the fuelrnassemblies are usually assumed to be vertical beams, supportedrnat both ends. Non-linear calculations are performed tornevaluate the impacts between assemblies, at the level of thernmixing grids.rnThis paper proposes an improved approach, recentlyrnimplemented in the CLASH 2.00 computer program, for thernpurpose of evaluating the seismic behavior of PWR cores andrnspent fuel racks for wet storage .rnThis method represents each fuel assembly as a pair of beams:rn· The first represents the skeleton, i.e. the guide tubes, therngrids, the head and the foot. It is relatively rigid andrnlightweight.rn· The second beam models the fuel rods only.rnIts mass is large but its rigidity is comparatively small.rnSprings link the two beams at the level of each mixing grid.rnNon-linear relationships describe these springs by relatingrntheir compression force to average depression.rnFor small deformations, the relationship reflects the totalrnstiffness of the actual springs, at a given grid level.For larger deformations, it can simulate the permanentrndeformations or even the collapse of the springs.rnThis Double Beam Model was first tested on several simplernbenchmarks, to qualify the code according to ISO 9001rnstandards.rnThe model was then compared to the classical Single BeamrnModel.rnThe sensitivity of the seismic response to burn-up could bernexamined only with the Double Beam Model. A fresh fuelrncase took into account a nominal spring pressure on the rods.rnIt was compared with a case featuring totally flat springs, i.e.rnthe situation when the burn-up is significant.rnAll the non-linear calculations presented are based onrnartificial accelerograms. These are randomly generated fromrna relevant response spectrum.rnThe results of a given simulation depend, to a large extent, onrnthe numeric trigger used to randomly generate the artificialrnaccelerograms. Each calculation case was thus evaluated withrn30 different accelerograms, to minimize the uncertainties inrnthe conclusions drawn from this preliminary investigation.
机译:分析压水反应堆标准堆芯的抗震性能主要是为了评估混合格栅和燃料棒的完整性。rn为了进行这种机械分析,通常将燃料组件假定为垂直梁,两端支撑。为了在混合网格的水平上执行非线性计算以评估组件之间的影响。本文提出了一种改进的方法,最近在CLASH 2.00计算机程序中实现了该方法,用于评估压水堆堆芯和湿式燃料架子的抗震性能。 .rn此方法将每个燃料组件表示为一对梁:rn·第一个代表骨架,即导管,tubes节,头部和足部。它相对刚性且重量轻。第二个梁仅对燃料棒建模。质量大但刚度相对较小。弹簧在两个混合网格的水平处将两个梁连接起来。非线性关系通过关联它们来描述这些弹簧。对于较小的变形,该关系反映了给定网格水平下实际弹簧的总刚度;对于较大的变形,该关系可以模拟弹簧的永久变形甚至坍塌。在几个简单的基准上,按照ISO 9001rnstandards对代码进行鉴定。然后将该模型与经典的Single BeamrnModel进行比较。rn仅使用Double Beam模型可以检查地震反应对燃尽的敏感性。新鲜燃料的情况下考虑了杆上的名义弹簧压力.rn与具有完全扁平弹簧的情况(即燃尽严重的情况)进行了比较.rn所有呈现的非线性计算均基于人工加速图。这些是从相关的响应谱中随机生成的。给定模拟的结果在很大程度上取决于用于随机生成人工加速度图的数字触发器。因此,使用30个不同的加速度图对每个计算案例进行了评估,以最大程度地减少初步研究得出的结论中的不确定性。

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