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GENERATION OF SFR PHYSICS MODELS FOR THE NUCLEAR FUEL CYCLE CODE CLASS

机译:核燃料循环代码类的SFR物理模型的生成

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This participation to PHYSOR 2016 aims to present the methods used to add a full description of a Sodium Fast Reactor (SFR) in the nuclear fuel cycle code CLASS. This description requires two models.The first one manage the determination of the plutonium content in the fresh fuel needed to meet a reactivity criterion according the composition of the available plutonium and depleted uranium storages. The second one aims to predict neutron spectrum averaged cross section needed to solves Bateman equations without calling a neutron transport code. The approach used to create this two models and their performances are shown. Furthermore, the impact of using time independent mean cross sections in the depletion calculation is depicted. These two models are based on applications of machine learning algorithms on a set of depletion calculations. The discrepancies on mean cross sections predicted by the model leads to relatively small errors on nuclei inventories at end of cycle. Indeed, the maximum difference in nuclei inventories calculated with the reference depletion code and CLASS using predicted mean cross sections is 2% for the main nuclei. The accuracy, relatively to the neutron transport code, of the k_(eff) predictor is about 130 pcm and allows to predict the plutonium content in the fresh fuel to meet k_(eff)(t= 0) at beginning of cycle.
机译:参加PHYSOR 2016旨在展示用于在核燃料循环代码CLASS中添加钠快速反应堆(SFR)完整描述的方法。该描述需要两个模型。第一个模型根据可用的and和贫铀库的组成来确定满足反应性标准所需的新鲜燃料中的content含量。第二个目标旨在预测解决贝特曼方程式所需的中子谱平均横截面,而无需调用中子输运码。显示了用于创建这两个模型的方法及其性能。此外,还描述了在耗竭计算中使用与时间无关的平均横截面的影响。这两个模型基于机器学习算法在一组消耗计算上的应用。该模型预测的平均横截面差异导致在周期结束时原子核清单的误差相对较小。的确,对于主核,用参考耗竭代码和CLASS使用预测的平均横截面计算的核库存最大差异为2%。 k_(eff)预测器的相对于中子输运代码的精度约为130 pcm,并允许预测新鲜燃料中cycle的含量,以在循环开始时满足k_(eff)(t = 0)。

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