KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
V. I. Belousov, V. D. Davidenko, I. I. Dyachkov, N. N. Elkin, M. R. Malkov, M. V. Ioannisian, M. G. Chernetskii, A. A. Chernitskaya, V. G. Zborovskii, V. V. Likhanskii, O. V. Khoruzhii
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引用次数: 0

Abstract

The paper considers the KIR-TG software package, which is designed for the interconnected neutron-physical and thermohydraulic test calculations of the infinite grid of VVER-SKD fuel elements. As part of the work, a software program written in the Python and Lua dynamic programming languages for linking between the module for calculating neutron physics (KIR computer program) and the TK-SKD thermohydraulic module was created and applied. The use of precision calculation performed by the Monte Carlo method in the neutron-physical part avoids the error of deterministic approximation methods in the calculation results. The problem statement, as well as the nature and results of the work, revealed the advantages of this approach to solving problems related to thermal-hydraulic calculations: parallel neutronic and sequential thermal-hydraulic calculations do not affect the overall speed of the associated calculation, the calculation codes are developed in parallel to save time and resources, and errors are tracked separately.

Abstract Image

用于 VVER-SKD 反应堆热液和中子物理试验计算的 KIR-TG 代码
本文讨论了 KIR-TG 软件包,该软件包设计用于对 VVER-SKD 燃料元件的无限网格进行相互关联的中子物理和热液压试验计算。作为工作的一部分,创建并应用了一个用 Python 和 Lua 动态编程语言编写的软件程序,用于连接中子物理计算模块(KIR 计算机程序)和 TK-SKD 热液压模块。在中子物理部分使用蒙特卡罗方法进行精确计算,避免了确定性近似方法在计算结果中产生的误差。问题陈述以及工作的性质和结果揭示了这种方法在解决与热液压计算有关的问题方面的优势:并行中子物理计算和顺序热液压计算不会影响相关计算的整体速度,并行开发计算代码以节省时间和资源,并分别跟踪误差。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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