Xenofontos Thalia, Savva Panayiota, M. Varvayanni, J. Maillard, J. Silva, N. Catsaros
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引用次数: 1
摘要
在核反应堆的设计和实际运行过程中,最重要的安全参数之一是调整控制棒以达到临界状态。关于常规核系统,通过使用确定性或随机性的中子学代码来指定其棒的位置,如今被认为是微不足道的。然而,加速器驱动系统等创新核反应堆概念需要复杂的随机中子学代码模拟能力,因为它们将散裂产生的中子的高能物理与经典核技术相结合。ANET(Advanced Neutronics with Evolution and Thermal hydraulic feedback)是一个正在开发的随机中子学代码,能够覆盖ADS系统中涉及的宽中子能谱,因此能够模拟常规和混合核反应堆并计算重要的反应堆参数。在这项工作中,检验了ANETS计算包含京都大学临界组件控制棒的三个核心配置的有效倍增因子的可靠性。ANET的结果成功地与诸如MCNP6.1之类的公认随机代码产生的结果进行了比较。
Criticality Search of an Accelerator Driven System Using the ANET Code
One of the most important safety parameters taken into consideration during the design and actual operation of a nuclear reactor is its control rods adjustment to reach criticality. Concerning the conventional nuclear systems, the specification of their rods’ position through the utilization of neutronics codes, deterministic or stochastic, is considered nowadays trivial. However, innovative nuclear reactor concepts such as the Accelerator Driven Systems require sophisticated simulation capabilities of the stochastic neutronics codes since they combine high energy physics, for the spallation-produced neutrons, with classical nuclear technology. ANET (Advanced Neutronics with Evolution and Thermal hydraulic feedback) is an under development stochastic neutronics code, able to cover the broad neutron energy spectrum involved in ADS systems and therefore capable of simulating conventional and hybrid nuclear reactors and calculating important reactor parameters. In this work, ANETS’s reliability to calculate the effective multiplication factor for three core configurations containing control rods of the Kyoto University Critical Assembly, an operating ADS, is examined. The ANET results successfully compare with results produced by well-established stochastic codes such as MCNP6.1.