| 核电站数字化仪控系统开发过程及其验证与确认 |
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| 引用本文： | 王翠芳. 核电站数字化仪控系统开发过程及其验证与确认[J]. 自动化仪表, 2012, 33(7): 49-52 |
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| 作者姓名： | 王翠芳 |
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| 作者单位： | 上海核工程研究设计院,上海,200233 |
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| 摘 要： | 分析了三代非能动型压水堆核电站AP1000的数字化仪控系统的开发过程模型,研究了与其开发过程紧密结合的验证与确认技术(V&V),特别是其审查、分析以及测试方法的使用,并提出了设计、测试及V&V过程的文档要求。该开发过程模型和V&V技术具有广泛的工业规范和标准认可度,对于我国自主化的核安全级数字化仪控系统的开发和取证具有重要的借鉴和指导意义。
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| 关 键 词： | AP1000 核电站 数字化仪控系统 验证与确认(V&V) V模型 |
Development Process,Verification & Validation of the Digitized Instrument & Control System for Nuclear Power Plant |
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| Wang Cuifang. Development Process,Verification & Validation of the Digitized Instrument & Control System for Nuclear Power Plant[J]. Process Automation Instrumentation, 2012, 33(7): 49-52 |
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| Authors: | Wang Cuifang |
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| Affiliation: | Wang Cuifang |
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| Abstract: | The models of development process of digitized instrument and control systems for three generations of AP1000 passive pressurized water reactor nuclear power plants are analyzed,and their closely related verification and validation(V&V) technology,especially the methods of review,analysis and test are researched.In addition,the requirements of the documentations in design,test and V&V processes are proposed.The development processing model and V&V technology are widely acceptable to industrial specifications and standards,they provide significant reference and guidance for developing and certificating of domestic digitized instrument and control systems conforming nuclear safety grade. |
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| Keywords: | AP1000 Nuclear power plant Digitized instrument and control system Verification and validation(V&V) V model |
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