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首页> 外文会议>PHYSOR 2004 - the physics of fuel cycles and advanced nuclear systems: global developments >BN-600 Full MOX Core Benchmark Analysis
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BN-600 Full MOX Core Benchmark Analysis

机译：BN-600全MOX核心基准分析

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As a follow-up of the BN-600 hybrid core benchmark, a full MOX core benchmark wasrnperformed within the framework of the IAEA co-ordinated research project. Discrepanciesrnbetween the values of main reactivity coefficients obtained by the participants for the BN-600rnfull MOX core benchmark appear to be larger than those in the previous hybrid corernbenchmarks on traditional core configurations. This arises due to uncertainties in the properrnmodelling of the axial sodium plenum above the core. It was recognized that the sodiumrndensity coefficient strongly depends on the core model configuration of interest (hybrid core vs.rnFully MOX fuelled core with sodium plenum above the core) in conjunction with therncalculation method (diffusion vs. transport theory).rnThe effects of the discrepancies revealed between the participants’ results on the ULOF andrnUTOP transient behaviours of the BN-600 full MOX core were investigated in simplifiedrntransient analyses. Generally the diffusion approximation predicts more benign consequencesrnfor the ULOF accident but more hazardous ones for the UTOP accident when compared withrnthe transport theory results. The heterogeneity effect does not have any significant effect on thernsimulation of the transient. The comparison of the transient analyses results concluded that thernfuel Doppler coefficient and the sodium density coefficient are the two most importantrncoefficients in understanding the ULOF transient behaviour. In particular, the uncertainty inrnevaluating the sodium density coefficient distribution has the largest impact on the descriptionrnof reactor dynamics. This is because the maximum sodium temperature rise takes place at therntop of the core and in the sodium plenum.
机译：作为BN-600混合动力核心基准测试的后续行动，在国际原子能机构协调研究项目的框架内执行了完整的MOX核心基准测试。参与者获得的BN-600rnfull MOX核心基准测试的主要反应系数之间的差异似乎大于以前在传统核心配置下的混合核心基准测试中的差异。这是由于岩心上方的轴向钠气室的固有模型的不确定性而产生的。公认的是，钠密度系数在很大程度上取决于目标岩心模型的配置（混合岩心vs.rn充分富氧的MOX燃料岩心，其中有更高的钠气室）结合计算方法（扩散与运输理论）.rn通过简化的瞬态分析，研究了参与者关于ULN和BN-600全MOX磁芯的​​UTOP瞬态行为之间的结果。一般而言，与运输理论结果相比，扩散近似预测对ULOF事故的危害更大，而对UTOP事故的危害更大。异质性效应对瞬态的模拟没有显着影响。瞬态分析结果的比较得出结论，燃料多普勒系数和钠密度系数是理解ULOF瞬态行为的两个最重要的系数。特别是，不确定钠密度系数分布的不确定性对反应堆动力学的描述影响最大。这是因为最大的钠温升发生在核心的顶部和钠腔中。

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