首页> 外文会议>American Nuclear Society;International Nuclear Fuel Cycle Conference;Light Water Reactor Fuel Performance Conference >A 2-D CORRELATION TO EVALUATE FUEL-CLADDING GAP THERMAL CONDUCTANCE IN MIXED OXIDE FUEL ELEMENTS FOR SODIUM-COOLED FAST REACTORS
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A 2-D CORRELATION TO EVALUATE FUEL-CLADDING GAP THERMAL CONDUCTANCE IN MIXED OXIDE FUEL ELEMENTS FOR SODIUM-COOLED FAST REACTORS

机译:二维相关性评估钠冷却快速反应器中混合氧化物燃料元件中的熔覆间隙热导率

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The paper defines a parameterization for thefuel-cladding gap thermal conductance in a SodiumCooled Fast Reactor. This collaboration took place withinthe EU-funded ESFR-SMART project.This requires use of predictive codes that have beenvalidated where possible against experimental data. Thisstudy relied on 7 fuel performance codes thus providingconfidence in the recommended correlation.A single pin model for both the inner and outer fuel wasbuilt. The fuel was burned for 2100 Effective Full PowerDays, with the axial power distribution varying over time.This paper presents a comparison between the codes’results and a 2-D correlation for the heat conductancewith respect to fuel burn-up and fuel rating. The fuel isbroken down into nodes with specific fuel rating andburn-up, leading to the gap conductance expressed as afunction of nodal fuel rating and burn-up. Data was thencompiled for all the nodes, for both fissile and fertileregions, for both inner and outer fuel for all 7 codes. A2D fit was applied to the data thus obtained.The results obtained show a general increase of heat conductance with fuel rating and burn-up, from 0.22 at 0 burn-up and 10kW. m~(-1) to 0.45 W. cm~(-2).K~(-1) at 0 burn-up and 50 kW. m~(-1) and to 1.00 W.cm~(-2).K~(-1) at 150 GWd.t~(-1) and 50 kW. m~(-1). Some spread between codes has been noted and appears to be consistent with the spread published earlier by several code developers.Sensitivity to various modelling assumptions is under investigation. This is aided by the use of numerous fuel performance codes which enables a wide ranging and thorough sensitivity analysis.
机译:该文件为 钠中的燃料包层间隙导热系数 冷却快堆。这项合作发生在 欧盟资助的ESFR-SMART项目。 这需要使用已经 根据实验数据进行了验证。这 该研究依赖于7个燃油性能规范,从而提供了 对推荐相​​关性的信心。 内部和外部燃料的单销模型是 内置的。燃料燃烧了2100有效满功率 天,轴向功率分布随时间变化。 本文对代码之间的比较进行了比较 结果和热导率的二维相关性 关于燃油消耗和燃油等级。燃料是 分解为具有特定燃油额定值的节点,并 耗尽,导致间隙电导表示为 节点燃油额定值和燃耗的功能。当时的数据 为所有节点(裂变和肥沃)编译 所有7个代码的内部和外部燃料区域。一种 将2D拟合应用于由此获得的数据。获得的结果表明,导热率随燃料额定值和燃耗而普遍增加,从0燃耗和10kW时的0.22开始。在0燃耗和50 kW下,m〜(-1)至0.45 W. cm〜(-2).K〜(-1)。在150 GWd.t〜(-1)和50 kW下达到m〜(-1)和1.00 W.cm〜(-2).K〜(-1)。 m〜(-1)。已经注意到代码之间的某些差异,并且似乎与一些代码开发人员早先发布的差异一致。 对各种建模假设的敏感性正在研究中。这得益于众多燃油性能代码的使用,这些代码可进行广泛的范围和彻底的灵敏度分析。

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