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Analysis of IPWR neutronic-thermohydraulic operation characteristics under low power condition

机译:低功率工况下IPWR中子热工运行特性分析

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摘要

In nuclear industry, using coupling of different best estimate 3-D neutron kinetic (N-K) and thermal hydraulic (T-H) codes to analyze neutronic-thermohydraulic features of reactor core is one of the most concerned research areas, which could help improve simulation fidelity and optimize nuclear design. In this paper, to further understand low power operation features of Integral PWR-200 (IP200), the coupled code combining RELAP5 and 3-D two-group neutron diffusion code had been developed. This paper reported the detailed processing of synchronizing different time steps explicitly and spatial mapping between T-H and N-K codes. To verify and validate the coupled code, the benchmark test results showed good agreement with the existing Qinshan nuclear power plant (NPP) operation data. IP200's entire system and reactor core were modeled using the coupled code. The simulation tasks gave descriptions of different scenarios of operation strategies, including rated power, natural circulation (NC) and once-through steam generators' (OTSGs) group operation under low power conditions. For forced circulation (FC) operation, reactor power, coolant flow and temperature features were mainly influenced by fuel assembly enrichment, control rods configuration and pumps' thrust. Under 25%FP low power operation, NC showed different coupled effects with that of FC, whose above core features were mainly influenced by loss of pumps' driven force. Besides, 25%FP OTSGs group operation transient conquered secondary-side flow instability, but also characterized by a strongly asymmetric behavior of the primary system which was caused by non-uniform coolant temperature distribution at the core inlet. The coupled code improved simulation precision of different low power operation strategies under the premise that it could fully generalize characteristics and performance of the whole system. Furthermore, the obtained knowledge of coupled code provided a better understanding of integral pressurized water reactor (IPWR) operation features with strong neutronic-thermohydraulic coupling effects, which would be beneficial to improve coupling other codes in future work. (C) 2019 Elsevier Ltd. All rights reserved.
机译:在核工业中,使用不同的最佳估计3-D中子动力学(NK)和热工水力(TH)代码的耦合来分析反应堆堆芯的中子热液特征是最受关注的研究领域之一,有助于提高仿真保真度和优化核设计。在本文中,为了进一步了解集成式PWR-200(IP200)的低功率运行特性,已经开发了结合RELAP5和3-D两组中子扩散码的耦合码。本文报告了显式同步不同时间步的详细处理以及T-H和N-K码之间的空间映射。为了验证和验证耦合代码,基准测试结果与现有的秦山核电站(NPP)运行数据显示出良好的一致性。使用耦合代码对IP200的整个系统和反应堆核心进行了建模。仿真任务描述了不同的运行策略方案,包括额定功率,自然循环(NC)和低功率条件下的直通式蒸汽发生器(OTSGs)组运行。对于强制循环(FC)操作,反应堆功率,冷却剂流量和温度特征主要受燃料组件浓缩,控制杆配置和泵推力的影响。在25%FP低功率运行下,NC与FC表现出不同的耦合效应,其以上核心特征主要受泵驱动力损失的影响。此外,25%FP OTSGs组的运行瞬态克服了次级侧流的不稳定性,但其特征还在于一次系统的强烈不对称行为,这是由堆芯入口处冷却液温度分布不均匀引起的。耦合代码在可以充分概括整个系统的特性和性能的前提下,提高了不同低功耗操作策略的仿真精度。此外,获得的耦合代码知识可以更好地理解具有强大的中子-热液耦合效应的整体压水堆(IPWR)操作功能,这将有利于在将来的工作中改善其他代码的耦合。 (C)2019 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2019年第7期|146-159|共14页
  • 作者单位

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

    Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Heilongjiang, Peoples R China;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Integral pressurized water reactor; RELAP5/N-K coupled code; Low power operation; Natural circulation; OTSGs group operation;

    机译:整体压水堆;RELAP5 / N-K耦合代码;低功率运行;自然循​​环;OTSGs组运行;

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