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首页> 外文会议>International conference on the physics of reactors;PHYSOR 08 >Analysis of Random-Loading HTR-PROTEUS Cores with Continuous Energy Monte Carlo Code Based on A Statistical Geometry Model
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Analysis of Random-Loading HTR-PROTEUS Cores with Continuous Energy Monte Carlo Code Based on A Statistical Geometry Model

机译：基于统计几何模型的连续能量蒙特卡罗代码随机加载HTR-PROTEUS堆芯分析

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Spherical elements have remarkable features in various applications in the nuclear engineering field. In 1990s, by the project of HTR-PROTEUS at PSI various pebble bed reactor experiments were conducted including cores with a lot of spherical fuel elements loaded randomly. In this study, criticality experiments of the random-loading HTR-PROTEUS cores were analyzed by MCNP-BALL, which could deal with a random arrangement of spherical fuel elements exactly with a statistical geometry model. As a result of analysis, the calculated effective multiplication factors were in fairly good agreement with the measurements within about 0.5%Ak/k. In comparison with other numerical analysis, our effective multiplication factors were between the experimental values and the VSOP calculations. To investigate the discrepancy of the effective multiplication factors between the experiments and calculations, sensitivity analyses were performed. As the result, the sensitivity of impurity boron concentration was fairly large. The reason of the present slight overestimation was not made clear at present. However, the presently existing difference was thought to be related to the impurity boron concentration, not to the modelling of the reactor and the used nuclear data. From the present study, it was confirmed that MCNP-BALL would have an advantage to conventional transport codes by comparing with their numerical results and the experimental values. As for the criticality experiment of PROTEUS, we would conclude that the two cores of Core 4.2 and 4.3 could be regarded as an equivalent experiment of a reference critical core, which was packed in the packing fraction of RLP.
机译：球形元件在核工程领域的各种应用中具有显着的特征。在1990年代，根据PSI的HTR-PROTEUS项目，进行了各种卵石床反应器实验，包括堆芯随机装载许多球形燃料元件的堆芯。在这项研究中，通过MCNP-BALL分析了随机加载的HTR-PROTEUS堆芯的临界实验，该实验可以使用统计几何模型精确地处理球形燃料元件的随机排列。分析的结果是，计算出的有效乘数与测量值在约0.5％Ak / k之内相当吻合。与其他数值分析相比，我们的有效倍增系数介于实验值​​和VSOP计算之间。为了调查实验和计算之间有效乘数因子的差异，进行了敏感性分析。结果，杂质硼浓度的灵敏度相当大。目前尚不清楚目前稍有高估的原因。但是，目前存在的差异被认为与杂质硼浓度有关，与反应堆的建模和所用的核数据无关。从本研究中可以证实，通过将MCNP-BALL的数值结果和实验值进行比较，它将比常规的运输代码更具优势。至于PROTEUS的关键性实验，我们可以得出结论，核心4.2和4.3的两个核心可以看作是参考关键核心的等效实验，它被封装在RLP的包装分数中。

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