| 基于FPGA的反应堆保护系统可靠性建模与分析 |
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| 引用本文： | 吕炜枫,熊 军,刘 杰,唐邵华. 基于FPGA的反应堆保护系统可靠性建模与分析[J]. 核动力工程, 2021, 41(5): 173-177. DOI: 10.13832/j.jnpe.2021.05.0173 |
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| 作者姓名： | 吕炜枫 熊 军 刘 杰 唐邵华 |
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| 作者单位： | 1.上海市电站自动化技术重点实验室，上海，200090 |
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| 摘 要： | 为建立基于现场可编程门阵列（FPGA）的反应堆保护系统的可靠性模型，以对系统安全提供有效的分析与验证手段。本研究采用故障树、随机Petri网模型，对CANDU堆1号停堆系统（SDS1）单通道进行可靠性建模与分析。对故障树模型分析得到最小割集，以顶事件发生概率作为系统故障概率，在考虑故障检测、维修与定期试验情况下对随机Petri网模型进行仿真得到系统的拒动概率。研究结果表明，故障树和状态空间方法存在一定局限性，随机Petri网能够反映故障检测与定期试验对反应堆保护系统的影响，可以动态地反映系统可靠性，并且避免了状态空间爆炸问题。因此，本研究建立的随机Petri网模型适用于反应堆保护系统的可靠性建模。
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| 关 键 词： | 反应堆保护系统 现场可编程门阵列（FPGA） 可靠性 故障树 随机Petri网 |
| 收稿时间： | 2020-07-24 |
Requirements for Monte Carlo Method during Radiation Shielding Optimization Design of Advanced PWR Nuclear Power Plants |
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| Lyu Weifeng,Xiong Jun,Liu Jie,Tang Shaohua. Requirements for Monte Carlo Method during Radiation Shielding Optimization Design of Advanced PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2021, 41(5): 173-177. DOI: 10.13832/j.jnpe.2021.05.0173 |
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| Authors: | Lyu Weifeng Xiong Jun Liu Jie Tang Shaohua |
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| Affiliation: | 1.Shanghai Key Laboratory of Power Station Automation Technology, Shanghai, 200090, China2.College of Automation Engineering, Shanghai University of Electric Power, Shanghai, 200090, China |
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| Abstract: | Based on the analysis of the problems resulting from the tool limitations during the radiation shielding design of M310 nuclear power plant and the requirements presented by the radiation shielding design of HPR1000 nuclear power plant, the requirements for Monte Carlo(MC) method during the optimization design of the radiation shielding for advanced PWR nuclear power plant are presented from four aspects, which are the software interface, input interface, dose rate calculation function and radiation field application expansion. The radiation shielding optimization design practice based on MC method in HPR1000 nuclear power plant shows that, by the development of the software interface, input interfaces and radiation field application expansion, the calculation code based on MC method can play a key role in the radiation shielding optimization design of advanced PWR nuclear power plant, and significantly improve the radiation shielding optimization design of PWR nuclear power plant. |
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