基于反应堆调节系统响应的CANDU反应堆建模的TRACE/PARCS ECI能力开发与测试

IF 1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY
S. Younan, D. Novog
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引用次数: 1

摘要

在CANDU反应堆的耦合安全性分析中,考虑了使用美国核管理委员会的代码TRACE和PARCS。CANDU模拟的一个关键因素是CANDU反应堆调节系统(RRS)的热工和物理现象之间的相互作用。迄今为止,TRACE-PARCS在这方面没有或只有有限的发展。在本工作中,系统热工代码TRACE_Mac1.0与核心物理代码PARCS_Mac1.0原生耦合,并通过TRACE中的外部通信接口(ECI)实现RRS控制。ECI用于将外部代码耦合到TRACE,包括附加的物理模型和控制系统模型。在这项工作中,开发了TRACE ECI库的Python接口,以及用Python编写的RRS模型。这种耦合使用CANDU-6 IAEA代码耦合基准和900 MW CANDU模型进行了各种瞬变测试。对于CANDU-6基准测试,瞬态不包括RRS响应,但是,将TRACE_Mac1.0/PARCS_Mac1.0耦合和ECI脚本功能与先前使用外部耦合的基准测试模拟进行了比较。对于900mw CANDU模拟,ECI模块和RRS的所有方面都包括在内。使用内置耦合时,CANDU-6基准测试的结果与之前使用两个代码之间的外部耦合所获得的结果相当,耦合模拟的执行时间减少了2倍到3倍。900 MW CANDU模拟成功地证明了RRS在流动损失事件中的功能,并且耦合解决方案在8字形流动不稳定性建模中表现出足够的性能。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response
The use of the USNRC codes TRACE and PARCS has been considered for the coupled safety analysis of CANDU reactors. A key element of CANDU simulations is the interactions between thermal-hydraulic and physic phenomena with the CANDU reactor regulating system (RRS). To date, no or limited development has taken place in TRACE-PARCS in this area. In this work, the system thermal-hydraulic code TRACE_Mac1.0 is natively coupled with the core physic code PARCS_Mac1.0, and RRS control is implemented via the exterior communications interface (ECI) in TRACE. ECI is used for coupling the external codes to TRACE, including additional physical models and control system models. In this work, a Python interface to the TRACE ECI library is developed, along with an RRS model written in Python. This coupling was tested using a CANDU-6 IAEA code coupling benchmark and a 900 MW CANDU model for various transients. For the CANDU-6 benchmark, the transients did not include RRS response, however, the TRACE_Mac1.0/PARCS_Mac1.0 coupling and ECI script functionality was compared to the previous benchmark simulations, which utilized external coupling. For the 900 MW CANDU simulations, all aspects of the ECI module and RRS were included. The results from the CANDU-6 benchmark when using the built-in coupling are comparable to those previously achieved using external coupling between the two codes with coupled simulations taking 2x to 3x less execution time. The 900 MW CANDU simulations successfully demonstrate the RRS functionality for the loss of flow events, and the coupled solutions demonstrate adequate performance for figure-of-eight flow instability modeling.
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来源期刊
Science and Technology of Nuclear Installations
Science and Technology of Nuclear Installations NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.30
自引率
9.10%
发文量
51
审稿时长
4-8 weeks
期刊介绍: Science and Technology of Nuclear Installations is an international scientific journal that aims to make available knowledge on issues related to the nuclear industry and to promote development in the area of nuclear sciences and technologies. The endeavor associated with the establishment and the growth of the journal is expected to lend support to the renaissance of nuclear technology in the world and especially in those countries where nuclear programs have not yet been developed.
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