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首页> 外文期刊>World Journal of Nuclear Science and Technology >Qualification of the ANET Code for Spallation Neutron Yield and Core Criticality in the KUCA ADS
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Qualification of the ANET Code for Spallation Neutron Yield and Core Criticality in the KUCA ADS

机译：KUCA ADS中散裂中子产率和核心临界度的ANET规范的资格

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Innovative nuclear reactor concepts such as the Accelerator Driven Systems (ADSs) have imposed extra requirements of simulation capabilities on the existing stochastic neutronics codes. The combination of an accelerator and a nuclear reactor in the ADS requires the simulation of both subsystems for an integrated system analysis. Therefore, a need arises for more advanced simulation tools, able to cover the broad neutron energy spectrum involved in these systems. ANET (Advanced Neutronics with Evolution and Thermal hydraulic feedback) is an under development stochastic code for simulating conventional and hybrid nuclear reactors. Successive testing applications performed throughout the ANET development have been utilized to verify and validate the new code capabilities. In this context, the ANET reliability in simulating the spallation reaction and the corresponding neutron yield as well as computing the multiplication factor of an operating ADS are here examined. More specifically, three cores of the Kyoto University Critical Assembly (KUCA) facility in Japan were analyzed focusing on the spallation neutron yield and the neutron multiplication factor. The ANET-produced results are compared with independent results obtained using the stochastic codes MCNP6.1 and MCNPX. Satisfactory agreement is found between the codes, confirming thus ANET’s capability to successfully estimate both the neutron yield of the spallation reaction and the k_(eff) of a realistic ADS.
机译：诸如加速器驱动系统（ADSs）之类的创新性核反应堆概念对现有的随机中子学代码施加了额外的仿真能力要求。 ADS中加速器和核反应堆的组合要求对两个子系统进行仿真，以进行集成系统分析。因此，需要能够覆盖这些系统所涉及的广泛的中子能谱的更先进的仿真工具。 ANET（具有演化和热力液压反馈的先进中子学）是一种用于模拟常规和混合核反应堆的正在开发的随机代码。在整个ANET开发过程中执行的连续测试应用程序已用于验证和验证新的代码功能。在这种情况下，本文研究了模拟散裂反应和相应的中子产率以及计算运行中的ADS的倍增因子时ANET的可靠性。更具体地说，分析了日本京都大学临界装配（KUCA）设施的三个核心，重点是散裂中子产量和中子倍增因子。将ANET产生的结果与使用随机代码MCNP6.1和MCNPX获得的独立结果进行比较。两者之间找到了令人满意的协议，从而确认了ANET能够成功估计散裂反应的中子产率和实际ADS的k_（eff）的能力。

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