Analysis of double-ended guillotine break accident of surge line in ACP100 based on coupling method: Development and validation of the coupling method

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Technology Pub Date : 2024-07-22 DOI:10.1016/j.net.2024.07.046

Fan Miao , Bin Zhang , Tianci Xie , Hao Yang , Jianqiang Shan

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Abstract

The ACP100 is a small modular reactor (SMR) designed and built in China, featuring an integrated primary loop and passive safety systems. In SMRs, the interaction between the reactor coolant system, containment vessel, and other systems is highly interdependent. Therefore, it is necessary to use high-precision analysis codes, which can be achieved by coupling multiple codes. This paper is the first part of a study which investigates the LOCA in the ACP100 using a coupled platform. In this paper, a coupling platform was developed for transient analysis of SMR accidents, based on the system code NUSOL-SYS and the Integrated Severe Accident Analysis (ISAA) code. An inter-process communication module was developed adopting shared memory and event objects to exchange data between the two codes. A coupling interface defining the data to be exchanged was proposed. Both NUSOL-SYS and ISAA were modified to perform synchronous time step control. The coupling platform were validated through a hypothetical scenario and Edwards’ pipe blowdown experiment, demonstrating exact consistency and high accuracy. This coupling platform offers a new method for SMR accident analysis, providing a foundation for future work.

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基于耦合法分析 ACP100 中浪涌线的双端铡刀断裂事故：耦合方法的开发与验证

ACP100 是中国设计和建造的小型模块化反应堆 (SMR)，具有集成的一次回路和被动安全系统。在 SMR 中，反应堆冷却剂系统、安全壳和其他系统之间的相互作用高度相互依赖。因此，有必要使用高精度的分析代码，这可以通过耦合多个代码来实现。本文是利用耦合平台研究 ACP100 LOCA 的第一部分。本文基于系统代码 NUSOL-SYS 和综合严重事故分析（ISAA）代码，开发了用于 SMR 事故瞬态分析的耦合平台。开发了一个进程间通信模块，采用共享内存和事件对象在两个代码之间交换数据。提出了一个定义要交换的数据的耦合接口。对 NUSOL-SYS 和 ISAA 都进行了修改，以执行同步时间步长控制。耦合平台通过假设场景和 Edwards 管道排污实验进行了验证，证明了其精确性和一致性。该耦合平台为 SMR 事故分析提供了一种新方法，为今后的工作奠定了基础。

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来源期刊

Nuclear Engineering and Technology 工程技术-核科学技术

CiteScore

4.80

自引率

7.40%

发文量

431

审稿时长

3.5 months

期刊介绍： Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development