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FISSION PRODUCT YIELDS COVARIANCE GENERATION METHODOLOGIES AND UNCERTAINTY PROPAGATION USING THE URANIE PLATFORM

机译:使用URANIE平台的裂变产品产量协方差生成方法和不确定性传播

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In modem nuclear technology, integral reactor parameter uncertainty evaluation plays a crucial role for both economical and safety purposes. Recent safety-by-design standards require strict margins of uncertainty, then intense activities of verification and validation are therefore necessary to ensure the precision needed for safe and sustainable modern technologies exploitation. The uncertainty associated to nuclear data plays a relevant role in this sense and many efforts have been recently spent to improve the whole input chain we provide to reactor code design procedures. Since some of them are not sufficiently detailed or even do not exist in modern nuclear data libraries yet, in this work we propose a methodology to generate, test and propagate covariance matrices for fission product yields. The main goal is to reproduce the JEFF-3.1.1 fission yields library and find associated covariances to be propagated using Monte Carlo and deterministic techniques in burn-up test-case calculations. Some results on the reactivity and decay heat uncertainty are presented for simple cases. Finally, a whole reactor geometries such as the Jules Horowitz Reactor (JHR), a material testing reactor under construction at CEA-Cadarache, is treated.
机译:在现代核技术中,整体堆反应堆参数不确定性评估对于经济和安全目的都起着至关重要的作用。最新的按设计安全标准要求严格的不确定性余量,因此必须进行大量的验证和确认活动,以确保安全和可持续的现代技术开发所需的精度。从这个意义上讲,与核数据有关的不确定性起着重要的作用,最近人们花费了很多努力来改善我们提供给反应堆代码设计程序的整个输入链。由于其中一些还不够详细,甚至在现代核数据库中都不存在,因此在这项工作中,我们提出了一种用于生成,测试和传播裂变产物产量的协方差矩阵的方法。主要目标是重现JEFF-3.1.1裂变产率库,并在燃烧测试用例计算中使用蒙特卡洛和确定性技术找到要传播的相关协方差。对于简单的情况,给出了一些有关反应性和衰变热不确定性的结果。最后,对整个反应堆的几何形状进行了处理,例如Jules Horowitz反应堆(JHR),这是CEA-Cadarache正在建设中的材料测试反应堆。

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