首页> 外文会议>International Nuclear Fuel Cycle Conference >VALIDATING THE FILL GAS THERMAL CONDUCTIVITY MODELS FOR GAP CONDUCTANCE CALCULATIONS IN NUCLEAR FUEL PERFORMANCE CODES
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VALIDATING THE FILL GAS THERMAL CONDUCTIVITY MODELS FOR GAP CONDUCTANCE CALCULATIONS IN NUCLEAR FUEL PERFORMANCE CODES

机译:核燃料绩效代码中的间隙电导计算验证填充气体导电模型

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The gap between fuel and cladding is initially pressurizedto prevent unstable thermal behavior and to maintain claddingintegrity. Helium is often chosen as the initial fill gas in nuclearfuel rods to improve the heat transfer through the gapbetween the fuel and the cladding. In light water reactors,this initial pressure ranges from 0.3 to 3.45 MPa and tendsto increase throughout the life of the reactor as a result ofexpansion/contraction of the fuel and cladding, fission gasrelease, and so on. In some cases, the rod internal pressureapproaches the external pressure or exceeds it. However, thepressure dependence of the thermal conductivity is neglectedin nuclear fuel performance codes at present. Current codesuse correlations that use only temperature and are calibratedto data at pressures below 0.1 MPa, but the pressure e ect issignificant on the thermal conductivity for the pressures above1.0 MPa. Therefore, the use of the current models in nuclearapplications, particularly in gap conductance calculations, isquestionable. This is examined herein. Theories related to gasproperties are presented, along with their validation againstliterature data for selected inert gases. Underlying assumptionsare clearly described for each model, and their possibleimpacts on gap conductance calculations are discussed. It isconcluded that the current approach in nuclear applicationsis only valid for helium; however, it is not valid in most gapconductance calculations once the gap is occupied mostly witheither lower conductivity gaseous fission products or an initialfill gas other than helium.
机译:最初加压燃料和包层之间的间隙防止不稳定的热行为并保持包层正直。氦气通常被选为核初始填充气体燃料棒通过间隙提高热传递在燃料和包层之间。在轻水反应器中,该初始压力范围为0.3至3.45MPa并趋于趋于因此,在反应堆的整个寿命中增加燃料和包层,裂变气体的扩展/收缩释放等等。在某些情况下,杆内部压力接近外部压力或超过它。然而导热率的压力依赖性被忽略了在目前的核燃料绩效代码中。当前代码使用仅使用温度并校准的相关性在低于0.1MPa的压力下的数据,但压力E ECT是关于上述压力的导热率显着1.0 MPa。因此,使用当前模型在核中应用,特别是在间隙导电计算中,是可疑的。这是在此检查的。与煤气有关的理论呈现属性,以及他们的验证所选惰性气体的文献数据。潜在的假设每个模型都清楚地描述,他们可能讨论了对差距传导计算的影响。这是结论是当前核应用的方法仅适用于氦气;但是,它在大多数差距都没有有效一旦间隙占据了主要占用的电导计算较低的导电性气体裂变产品或初始氦以外的汽油。

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