Article(id=1149769464771686777, tenantId=1146029695717560320, journalId=1146123166801305609, issueId=1149769458706723113, articleNumber=null, orderNo=null, doi=10.12404/j.issn.1671-1815.2404697, pmid=null, cstr=null, oa=null, hot=null, price=null, onlineType=0, articleFormat=0, articleType=null, articleTypeStr=null, receivedDate=1719072000000, receivedDateStr=2024-06-23, revisedDate=1740412800000, revisedDateStr=2025-02-25, acceptedDate=null, acceptedDateStr=null, onlineDate=1752056002084, onlineDateStr=2025-07-09, pubDate=1747497600000, pubDateStr=2025-05-18, doiRegisterDate=null, doiRegisterDateStr=null, onlineIssueDate=1752056002084, onlineIssueDateStr=2025-07-09, onlineJustAcceptDate=null, onlineJustAcceptDateStr=null, onlineFirstDate=null, onlineFirstDateStr=null, sourceXml=null, magXml=null, createTime=1752056002084, creator=13701087609, updateTime=1752056002084, updator=13701087609, issue=Issue{id=1149769458706723113, tenantId=1146029695717560320, journalId=1146123166801305609, year='2025', volume='25', issue='14', pageStart='5705', pageEnd='6154', issueExtLink='null', onlineDate='null', pubDate='null', beforeIssueId=null, nextIssueId=null, price=null, status=1, issueComplete=1, articleOrder=1, issueType=-1, specialIssue=0, createTime=1752056000638, creator=13701087609, updateTime=1768456798957, updator=13701087609, preIssue=null, nextIssue=null, ext={EN=IssueExt(id=1218559392753041779, tenantId=1146029695717560320, journalId=1146123166801305609, issueId=1149769458706723113, language=EN, specialIssueTitle=, coverIllustrator=, specialIssueEditor=, specialIssueAbout=), CN=IssueExt(id=1218559392753041780, tenantId=1146029695717560320, journalId=1146123166801305609, issueId=1149769458706723113, language=CN, specialIssueTitle=, coverIllustrator=, specialIssueEditor=, specialIssueAbout=)}, issueFiles=null}, startPage=5870, endPage=5876, ext={EN=ArticleExt(id=1149769465153368460, articleId=1149769464771686777, tenantId=1146029695717560320, journalId=1146123166801305609, language=EN, title=Application Study of Equipment Reliability Classification Method for Sodium-Cooled Fast Reactor, columnId=1156264259077137059, journalTitle=Science Technology and Engineering, columnName=Papers·Nuclear Technology, runingTitle=null, highlight=null, articleAbstract=

It is essential to perform equipment reliability classification in order to devote limited resources to NPP equipment management reasonably, improve equipment reliability and availability while reducing maintenance workload and cost, and enable NPP’s safe, reliable, and economical operation. In light of engineering characteristics of the demonstration fast reactor and the challenges during the construction, an attainable new method was developed to standardize the process of equipment reliability classification and complete the classification of all systems. The differences and characteristics among the methods were compared, the implementation process of the new method was proposed and demonstrated with two real systems. The application shows that the proposed method is efficient, effective and rational, hence can offer to assist other NPPs of similar reactors to implement reliability classification during NPP construction.

, correspAuthors=Xin-wen ZHAO, authorNote=null, correspAuthorsNote=null, copyrightStatement=null, copyrightOwner=null, extLink=null, articleAbsUrl=null, sourceXml=null, magXml=null, pdfUrl=null, pdf=null, pdfFileSize=null, pdfExtLink=null, richHtmlUrl=null, mobilePdfUrl=null, reviewReport=null, pdfFirstPage=null, abstractGraph=null, abstractGraphContent=null, abstractVideo=null, citation=null, cebUrl=null, magXmlContent=null, mapNumber=null, authorCompany=null, fund=null, authors=null, authorsList=Bing-yue LIU, Wei LIU, Xin-wen ZHAO, Chao CHEN, Lu WANG, Shao-you LIU, Bin KONG), CN=ArticleExt(id=1149769469385421246, articleId=1149769464771686777, tenantId=1146029695717560320, journalId=1146123166801305609, language=CN, title=钠冷快堆设备可靠性分级方法研究与应用, columnId=1156264259655951016, journalTitle=科学技术与工程, columnName=论文·原子能技术, runingTitle=null, highlight=null, articleAbstract=

为了将有限的资源合理地应用到核电厂设备管理工作中,提高设备的可靠性和可用性,降低设备检修工作量和成本,使电厂机组能够安全、可靠、经济地运行,有必要对设备进行可靠性分级管理。针对示范快堆工程建设期间的工作特点和挑战,研究并形成了适用的、可行的设备可靠性规范化分级新方法与流程。本文研究分析了其与已有方法的不同与特点,提出了新方法实施的工作流程,并以示范快堆两个实例系统为对象进行了应用说明。实践证明了该新方法的高效、合理与有效性,为后续处于建设阶段的同类堆型开展可靠性分级工作提供了方法与经验。

, correspAuthors=赵新文, authorNote=null, correspAuthorsNote=
*赵新文(1968—),男,汉族,河南信阳人,博士,教授。研究方向:核反应堆概率安全分析。E-mail:
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刘丙月(1984—),男,汉族,河北衡水人,博士研究生,高级工程师。研究方向:设备可靠性管理、维修决策。E-mail:

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刘丙月(1984—),男,汉族,河北衡水人,博士研究生,高级工程师。研究方向:设备可靠性管理、维修决策。E-mail:

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刘丙月(1984—),男,汉族,河北衡水人,博士研究生,高级工程师。研究方向:设备可靠性管理、维修决策。E-mail:

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College of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China), AuthorCompanyExt(id=1172852568972738882, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, companyId=1172852568955961664, language=CN, country=null, province=null, city=null, postcode=null, companyName=null, departmentName=null, remark=1. 海军工程大学核科学技术学院, 武汉 430033)]), AuthorCompany(id=1172852569023070531, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, xref=null, ext=[AuthorCompanyExt(id=1172852569039847748, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, companyId=1172852569023070531, language=EN, country=null, province=null, city=null, postcode=null, companyName=null, departmentName=null, remark=2. The Tenth Research Section, Wuhan Second Ship Design and Research Institute, Wuhan 430064, China), AuthorCompanyExt(id=1172852569048236357, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, companyId=1172852569023070531, language=CN, country=null, province=null, city=null, postcode=null, companyName=null, departmentName=null, remark=2. 武汉第二船舶设计研究所第十研究室, 武汉 430064)]), AuthorCompany(id=1172852569115345222, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, xref=null, ext=[AuthorCompanyExt(id=1172852569119539527, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, companyId=1172852569115345222, language=EN, country=null, province=null, city=null, postcode=null, companyName=null, departmentName=null, remark=3. Nuclear Power Maintenance Center, China Nuclear Power Operation Technology Co., Ltd., Wuhan 430223, China), AuthorCompanyExt(id=1172852569140511048, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, companyId=1172852569115345222, language=CN, country=null, province=null, city=null, postcode=null, companyName=null, departmentName=null, remark=3. 中核武汉核电运行技术股份有限公司维修中心, 武汉 430223)]), AuthorCompany(id=1172852569216008522, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, xref=null, ext=[AuthorCompanyExt(id=1172852569220202827, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, companyId=1172852569216008522, language=EN, country=null, province=null, city=null, postcode=null, companyName=null, departmentName=null, remark=4. Equipment Section,CNNP Xiapu Nuclear Power Co., Ltd., Ningde 355100, China), AuthorCompanyExt(id=1172852569224397132, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, companyId=1172852569216008522, language=CN, country=null, province=null, city=null, postcode=null, companyName=null, departmentName=null, remark=4. 中核霞浦核电有限公司设备处, 宁德 355100)])], figs=[ArticleFig(id=1172852571854225788, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=EN, label=Fig.1, caption=The overall comparison among three methods, figureFileSmall=q9Vej+6fW2GEJeD8BHeneA==, figureFileBig=s1CLOc9OPvh7JIiSEJdI2g==, tableContent=null), ArticleFig(id=1172852571975860605, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=CN, label=图1, caption=3种分级方法整体比较, figureFileSmall=q9Vej+6fW2GEJeD8BHeneA==, figureFileBig=s1CLOc9OPvh7JIiSEJdI2g==, tableContent=null), ArticleFig(id=1172852572034580862, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=EN, label=Table 1, caption=

Specific differences among three methods

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步骤 SRCM AP-913 新方法
3 在“系统”层面,判定“系统功能”关键度 在“设备”层面,将功能相关设备划组 在“系统”层面,利用“系统功能”判定“系统”关键度
4 从系统关键功能、重要功能出发识别设备关键度,是“自上而下”的分析 按照设备失效后果对应的识别条件判定关键度,是“自下而上”的分析 按照设备对系统和机组的失效后果,判定关键度,是“自下而上”的分析
), ArticleFig(id=1172852572084912511, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=CN, label=表1, caption=

3种方法的差异点分析

, figureFileSmall=null, figureFileBig=null, tableContent=
步骤 SRCM AP-913 新方法
3 在“系统”层面,判定“系统功能”关键度 在“设备”层面,将功能相关设备划组 在“系统”层面,利用“系统功能”判定“系统”关键度
4 从系统关键功能、重要功能出发识别设备关键度,是“自上而下”的分析 按照设备失效后果对应的识别条件判定关键度,是“自下而上”的分析 按照设备对系统和机组的失效后果,判定关键度,是“自下而上”的分析
), ArticleFig(id=1172852572164604288, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=EN, label=Table 2, caption=

Classification process of a critical system

, figureFileSmall=null, figureFileBig=null, tableContent=
设备
编码
设备
名称
关键
工作
频度
工作
环境
正常
状态
设备主要
功能
失效模式 是否
隐性
失效对系统功能影响 失效对
机组影响
关键度
代码
LAA
10BB
301
除氧器 CC2 H S 连续
运行
储存并提供合格的主给水给主给水泵前置泵 外漏,功能丧失,性能劣化,失去完整结构 外漏,失去完整结构导致不能储存及提供合格的主给水;考虑除氧器外漏发生概率低,即使外漏也不会立即导致停机停堆,属于风险重要设备,定级为CC2。性能劣化,功能丧失导致除氧器给水水质不合格 除氧器发生泄漏至低低水位概率低,属于风险重要设备 CC2-j属于风险重要(高风险)设备(CC1级设备除外)
LAA
10CL
101
除氧器水
位低低液
位开关
NC L M 不动作 在除氧器水位低低报警 不能开,不能关,堵塞,泄漏 提供液位低低报警,失效无法提供报警,增加运行负担 失效增加运行人员负担 NC-j导致失去重要报警或运行参数无法监视,增加运行人员负担
LAA
20AP
001
除氧器
循环泵
NC H M 连续
运行
对除氧器再循环给水提供动力 不能启动,性能劣化 除氧器给水无法再循环,机组启动延迟 失效影响机组启动 NC-k装换料设备或影响大修关键路径的设备
LAA
10AA
405
除氧器
安全阀E
NC L S 常关 防止除氧器超压 外漏,内漏,不能回座 失效不能开启将导致除氧器超压;不能回座将影响除氧器压力 如除氧器超压将导致设备损坏 NC-h属于工业安全等法规监管的设备
LAA
10AA
001
除氧器
放水阀
RTM L M 常关 对除氧器正常放水管路进行隔离 不能开关,内漏,外漏 不能隔离除氧器正常放水管路 对机组正常运行无影响 RTM-a所有不满足关键1级、关键2级和重要设备识别条件的设备
), ArticleFig(id=1172852572227518849, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=CN, label=表2, caption=

关键系统LAA详细分级过程(部分)

, figureFileSmall=null, figureFileBig=null, tableContent=
设备
编码
设备
名称
关键
工作
频度
工作
环境
正常
状态
设备主要
功能
失效模式 是否
隐性
失效对系统功能影响 失效对
机组影响
关键度
代码
LAA
10BB
301
除氧器 CC2 H S 连续
运行
储存并提供合格的主给水给主给水泵前置泵 外漏,功能丧失,性能劣化,失去完整结构 外漏,失去完整结构导致不能储存及提供合格的主给水;考虑除氧器外漏发生概率低,即使外漏也不会立即导致停机停堆,属于风险重要设备,定级为CC2。性能劣化,功能丧失导致除氧器给水水质不合格 除氧器发生泄漏至低低水位概率低,属于风险重要设备 CC2-j属于风险重要(高风险)设备(CC1级设备除外)
LAA
10CL
101
除氧器水
位低低液
位开关
NC L M 不动作 在除氧器水位低低报警 不能开,不能关,堵塞,泄漏 提供液位低低报警,失效无法提供报警,增加运行负担 失效增加运行人员负担 NC-j导致失去重要报警或运行参数无法监视,增加运行人员负担
LAA
20AP
001
除氧器
循环泵
NC H M 连续
运行
对除氧器再循环给水提供动力 不能启动,性能劣化 除氧器给水无法再循环,机组启动延迟 失效影响机组启动 NC-k装换料设备或影响大修关键路径的设备
LAA
10AA
405
除氧器
安全阀E
NC L S 常关 防止除氧器超压 外漏,内漏,不能回座 失效不能开启将导致除氧器超压;不能回座将影响除氧器压力 如除氧器超压将导致设备损坏 NC-h属于工业安全等法规监管的设备
LAA
10AA
001
除氧器
放水阀
RTM L M 常关 对除氧器正常放水管路进行隔离 不能开关,内漏,外漏 不能隔离除氧器正常放水管路 对机组正常运行无影响 RTM-a所有不满足关键1级、关键2级和重要设备识别条件的设备
), ArticleFig(id=1172852572332376450, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=EN, label=Table 3, caption=

Classification process of an important system

, figureFileSmall=null, figureFileBig=null, tableContent=
设备编码 设备名称 关键度 工作
频度
工作
环境
正常
状态
设备失效影响 关键度代码
LCU10AA301 10LCU10CF001
上游仪表根阀
RTM L M 常开 仪表根阀处于常开状态,故障后可以进行维修,不会对电厂运行产生重要影响 RTM-a所有不满足关键1级、关键2级和重要设备识别条件的设备
LCU10AA501 10LCU
管线疏水阀
RTM L M 常关 阀门处于常闭状态,疏水阀不能开启导致不能排出管线中的疏水,影响系统的在线,阀门可以及时进行维修,不会产生重要影响 RTM-a所有不满足关键1级、关键2级和重要设备识别条件的设备
LCU10CP001 10LCU入口
压力变送器
NC H M 连续运行 用于主控指示常规岛除盐水压力重要参数。压力变送器故障导致主控失去除盐水压力参数指示或指示异常,会增加运行人员负担 NC-j导致失去重要报警或运行参数无法监视,增加运行人员负担
), ArticleFig(id=1172852572382708099, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=CN, label=表3, caption=

重要系统LCU快速分级过程(部分)

, figureFileSmall=null, figureFileBig=null, tableContent=
设备编码 设备名称 关键度 工作
频度
工作
环境
正常
状态
设备失效影响 关键度代码
LCU10AA301 10LCU10CF001
上游仪表根阀
RTM L M 常开 仪表根阀处于常开状态,故障后可以进行维修,不会对电厂运行产生重要影响 RTM-a所有不满足关键1级、关键2级和重要设备识别条件的设备
LCU10AA501 10LCU
管线疏水阀
RTM L M 常关 阀门处于常闭状态,疏水阀不能开启导致不能排出管线中的疏水,影响系统的在线,阀门可以及时进行维修,不会产生重要影响 RTM-a所有不满足关键1级、关键2级和重要设备识别条件的设备
LCU10CP001 10LCU入口
压力变送器
NC H M 连续运行 用于主控指示常规岛除盐水压力重要参数。压力变送器故障导致主控失去除盐水压力参数指示或指示异常,会增加运行人员负担 NC-j导致失去重要报警或运行参数无法监视,增加运行人员负担
), ArticleFig(id=1172852572458205572, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=EN, label=Table 4, caption=

Statistics of the classification

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堆型 占比/%
CC1 CC2 NC RTM
钠冷快堆 0.36 3.12 59.47 37.06
某压水堆 1.0 4.0 26.8 68.2
), ArticleFig(id=1172852572563063173, tenantId=1146029695717560320, journalId=1146123166801305609, articleId=1149769464771686777, language=CN, label=表4, caption=

分级结果统计对比

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堆型 占比/%
CC1 CC2 NC RTM
钠冷快堆 0.36 3.12 59.47 37.06
某压水堆 1.0 4.0 26.8 68.2
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钠冷快堆设备可靠性分级方法研究与应用
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刘丙月 1, 2 , 刘伟 3 , 赵新文 1, * , 陈超 4 , 王璐 4 , 刘少有 2 , 孔斌 2
科学技术与工程 | 论文·原子能技术 2025,25(14): 5870-5876
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科学技术与工程 | 论文·原子能技术 2025, 25(14): 5870-5876
钠冷快堆设备可靠性分级方法研究与应用
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刘丙月1, 2 , 刘伟3, 赵新文1, * , 陈超4, 王璐4, 刘少有2, 孔斌2
作者信息
  • 1. 海军工程大学核科学技术学院, 武汉 430033
  • 2. 武汉第二船舶设计研究所第十研究室, 武汉 430064
  • 3. 中核武汉核电运行技术股份有限公司维修中心, 武汉 430223
  • 4. 中核霞浦核电有限公司设备处, 宁德 355100
  • 刘丙月(1984—),男,汉族,河北衡水人,博士研究生,高级工程师。研究方向:设备可靠性管理、维修决策。E-mail:

通讯作者:

*赵新文(1968—),男,汉族,河南信阳人,博士,教授。研究方向:核反应堆概率安全分析。E-mail:
Application Study of Equipment Reliability Classification Method for Sodium-Cooled Fast Reactor
Bing-yue LIU1, 2 , Wei LIU3, Xin-wen ZHAO1, * , Chao CHEN4, Lu WANG4, Shao-you LIU2, Bin KONG2
Affiliations
  • 1. College of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China
  • 2. The Tenth Research Section, Wuhan Second Ship Design and Research Institute, Wuhan 430064, China
  • 3. Nuclear Power Maintenance Center, China Nuclear Power Operation Technology Co., Ltd., Wuhan 430223, China
  • 4. Equipment Section,CNNP Xiapu Nuclear Power Co., Ltd., Ningde 355100, China
出版时间: 2025-05-18 doi: 10.12404/j.issn.1671-1815.2404697
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为了将有限的资源合理地应用到核电厂设备管理工作中,提高设备的可靠性和可用性,降低设备检修工作量和成本,使电厂机组能够安全、可靠、经济地运行,有必要对设备进行可靠性分级管理。针对示范快堆工程建设期间的工作特点和挑战,研究并形成了适用的、可行的设备可靠性规范化分级新方法与流程。本文研究分析了其与已有方法的不同与特点,提出了新方法实施的工作流程,并以示范快堆两个实例系统为对象进行了应用说明。实践证明了该新方法的高效、合理与有效性,为后续处于建设阶段的同类堆型开展可靠性分级工作提供了方法与经验。

钠冷快堆  /  可靠性分级  /  关键度  /  设备管理

It is essential to perform equipment reliability classification in order to devote limited resources to NPP equipment management reasonably, improve equipment reliability and availability while reducing maintenance workload and cost, and enable NPP’s safe, reliable, and economical operation. In light of engineering characteristics of the demonstration fast reactor and the challenges during the construction, an attainable new method was developed to standardize the process of equipment reliability classification and complete the classification of all systems. The differences and characteristics among the methods were compared, the implementation process of the new method was proposed and demonstrated with two real systems. The application shows that the proposed method is efficient, effective and rational, hence can offer to assist other NPPs of similar reactors to implement reliability classification during NPP construction.

sodium-cooled fast reactor  /  reliability classification  /  criticality  /  equipment management
刘丙月, 刘伟, 赵新文, 陈超, 王璐, 刘少有, 孔斌. 钠冷快堆设备可靠性分级方法研究与应用. 科学技术与工程, 2025 , 25 (14) : 5870 -5876 . DOI: 10.12404/j.issn.1671-1815.2404697
Bing-yue LIU, Wei LIU, Xin-wen ZHAO, Chao CHEN, Lu WANG, Shao-you LIU, Bin KONG. Application Study of Equipment Reliability Classification Method for Sodium-Cooled Fast Reactor[J]. Science Technology and Engineering, 2025 , 25 (14) : 5870 -5876 . DOI: 10.12404/j.issn.1671-1815.2404697
对事物进行分级的思想和方法已经应用在多个行业领域,如铁路[1]、电力[2]、矿业[3]、石油天然气[4]等。核电厂的生产设施由大大小小约300个“系统”组成,每个“系统”又由一定数量的“设备”及连接“设备”的管、线组成[5]。通常一个系统包含数百个设备,整个电厂的设备则数以万计。为合理分配核电厂的检修资源,确保对安全稳定经济运行重要的系统和设备得到充分重视,必须对电厂设备进行可靠性分级管理[6]。电厂多个业务领域的工作按照不同的设备等级投入相应的技术与管理资源,如:预防性维修[7]、预测性维修、寿期管理[8]、性能监测[9-10]、设计变更等。对不同等级的设备实施不同的管理要求,既有针对性地提高了核电厂的可靠性,又避免了对某些不重要设备过于关注的现象。
核电厂设备分级可以归纳为定性、定量两类方法。定量方法通常使用故障树(fault tree analysis,FTA)、概率安全分析(probabilistic safety assessment, PSA)[11-14]方法,如PSA使用割集重要度(fussell-vesely, FV)、风险增加当量重要度(risk achievement worth, RAW)两个重要度指标来分级。这些定量方法需要较好的模型基础和大量的历史运行失效信息,不适用于新研发或小众堆型。定性方法通过判断系统设备失效后果的严重程度进行分级,其中,以可靠性为中心的维修(reliability centered maintenance, RCM)经典方法从“系统”层面入手,进行系统功能失效分析,识别影响系统功能失效的“设备”故障模式,并据此制定适用的故障预防措施[15-16]。经典RCM通常不判定系统功能和设备的重要性(即关键度),不用于设备可靠性分级。精简型RCM(streamlined reliability centered maintenance, SRCM)判定系统功能和设备的重要性,可以用于设备可靠性分级[17]。但从系统功能来识别设备的关键度难度较大,很容易发生将相应设备排除在分析结果之外的情况[18]。秦凤等[19]采用了美国核动力运行研究所发布的核电厂设备可靠性管理流程(AP-913)中的可靠性分级方法,即直接从系统包含的设备清单入手,逐一分析清单中设备失效对电厂的影响,从而判定出设备的相应关键度级别。但该方法对系统内所有的设备同等对待,其分析需要较多的专业人员投入、耗时较长。
示范快堆具有“时间紧、任务重、挑战大”的特点。同时,由于中外钠冷快堆的小众性和特殊性,可以参考的资料相对较少、没有成熟经验可借鉴[20];从业人员较少、经验欠缺[21]。因此,需要在其他核电压水堆或者改进堆型的成熟分级方法基础上,进一步优化改进。
综上,基于示范快堆工程建设特点,现研究和借鉴SRCM和AP-913设备分级方法优势,探索设计一种适用于示范快堆的可靠性分级方法,形成规范化的分级流程。根据该方法完成示范快堆所有系统的设备可靠性分级,以期为工程建设期间的其他同类堆型开展设备可靠性分级工作提供参考。
面对示范快堆工程特点和资源约束,需要开发一种既快速可靠而又便于实施的方法。经过对比研究,形成了适用于钠冷快堆设备可靠性分级的新方法。为便于分析不同方法的区别与联系,将SRCM方法、AP-913方法和本研究的新方法归纳为主要的6步,如图1所示。
其中,SRCM方法步骤3“识别系统关键重要功能”按照系统功能失效后果分析将系统功能分为关键、重要和一般功能;步骤4“设备关键度分级”识别导致系统关键功能、重要功能失效的设备,由此判定出关键、重要和一般设备。AP-913方法步骤3“划分功能设备组”从设备清单入手,将影响到主设备功能运行的相关设备划为功能组;步骤4“设备关键度分级”按照设备失效后果对应的识别条件,判定出对应的设备关键度级别。新方法步骤3“系统关键度分级”按照系统功能失效后果分析,将系统分为关键、重要和一般系统;步骤4对关键、重要系统采用不同的“设备关键度分级”方法,一般系统原则上不开展“设备关键度分级”。
3种方法的主要区别在步骤3和步骤4两步,其对比分析如表1所示。可以看出,新方法具有如下2个特点。
(1)“两次”分级。SRCM方法在“设备”层面完成了关键度分级,即通过设备功能失效后果分析,将设备判定为关键、重要、一般。新方法借鉴其关键度分级的思想,除“设备”关键度分级之外,还进行了“系统”关键度分级,即通过系统功能失效后果分析,判定了“系统”的关键度,并根据系统关键度采用不同的“设备关键度分级”方法:对关键系统采用详细分级;对重要系统采用简化快速分级;对一般系统不分析,因此提高了工作效率。新方法比SRCM方法多了一次“系统”关键度分级,可简称为S2RCM。
(2)流程再造。新方法通过如上所述的“系统”关键度分级区别对待了“系统”内设备,设计了不同的设备分级操作过程和相应的表格,避免了AP-913方法对“系统内所有的设备同等对待”。同时,新方法关键、重要系统的设备关键度分级又借鉴了AP-913方法“自下而上”的分析,既能降低SRCM方法“自上而下”利用系统功能来识别关键设备的难度,也不容易遗漏设备。
在实际工作过程中,新方法6个步骤的具体操作如下。
在分析开始前,需要进行系统设备相关资料收集与准备。资料主要包括:系统设计手册、运行规程、最终安全分析报告、技术规范(technical specification, TS)、设备供应商手册、系统流程图、逻辑图等。
相比其他在运的压水堆机组,设计阶段示范快堆的系统划分颗粒度较小、稍显零散。为便于系统功能分析,保证功能的完整、独立,需要对系统进行合并。按照系统设计手册中的相应章节及系统流程图,分析系统的运行原理、功能与接口关系,将具有功能相关及接口关系的系统合并为一个新的系统。合并后系统按其主要功能进行中文命名,其英文编码则保留所有合并前各系统的已有英文编码,中间以“/”区分。
原则上,用于可靠性分级的系统边界和快堆设计时已有的系统边界划分保持一致。但若有与待分析系统功能和接口强相关的设备在相邻系统内,也应该把相应设备划分到待分析的系统边界内。
在设备关键度分级前,先通过系统功能失效后果分析判定系统的重要性,即按照系统功能失效后果的严重程度将系统分为三类,分别为关键系统、重要系统和一般系统。系统重要性判定目的是根据系统的重要程度,对其设备采用不同的关键度分级流程,即关键系统采用详细分级流程、重要系统采用快速分级流程、一般系统不开展设备分级,以便加快分级进度。
根据系统设计手册,分析系统所有功能。系统功能分析应尽可能全面、详细,综合考虑机组正常运行时的功能和机组瞬态时的功能;对每一项功能,分析其失效对系统及电厂造成的影响,然后对照关键度判断准则或识别条件,判定该功能的关键度级别。以该系统所有功能中关键度等级最高者,作为该系统的关键度级别。
对于识别出的关键系统,按如下步骤分析并完成设备分级。
(1)设备功能描述:参照系统设计手册,分析该设备所有功能,包括系统正常运行时设备具有的功能及发生紧急情况时的功能。
(2)主要故障模式分析:对应每一个功能,分析导致该设备功能失效的主要故障模式。在分析故障模式时,只考虑设备在该系统中可能发生或较为合理的故障。
(3)故障显隐性判断:如果单一故障的发生可以被履行正常职责的运行巡检人员明显发现,该故障是显性故障;如果单一故障的发生不能被运行人员明显发现,即不论是正常运行情况还是特殊运行情况,如果某个单一故障的发生都不会立即对系统的运行造成影响,则该故障为隐性故障。
(4)故障影响分析:故障影响包括对系统的影响和对电厂的影响。在分析影响时,以单一设备故障发生时导致后果的严重程度为基准。在考虑后果时,假设所有的热备用、冷备用、冗余、安装的备件都能满足要求的功能。
(5)设备关键度识别:按照设备失效对电厂造成的后果严重程度,将设备分为关键1级设备(critical component 1, CC1)、关键2级设备(CC2)、重要设备(non-critical, NC)和一般设备(run to maintenance, RTM)。
对于识别出的重要系统,根据设备正常运行状态,按照设备失效后对系统和机组造成的后果严重程度,对照设备关键度识别条件,判定设备关键度级别。
根据设备工作循环或加载的数量,工作频度[19]分两种类型:高(high, H)、低(low, L)。设备处于连续运行或频繁切换的工作状态(如:切换频率≥2次/周),视为工作频度高(H),其他的视为工作频度低(L)。
根据设备运行时的内部和外部环境的严重程度,工作环境[19]分两种类型:严酷(severity, S)、良好(medium, M)。
利用上节方法完成了示范快堆所有系统设备可靠性分级。以两个实例系统(编码分别为LAA、LCU)说明新方法的主要步骤,并统计分级结果、进行讨论。
分为机械边界、电气边界和仪控边界。以LAA系统为例,其中:①机械边界参照系统手册中的流程图划定,流程图上编码为LAA的所有设备均属于LAA系统;②电气边界参照系统手册中的流程图划定,包括流程图上编码为LAA的所有电机、电动隔离阀电动头的动力回路和控制回路;③仪控边界参照系统手册中的流程图划定,包括所有编码为LAA的就地指示仪表、送仪控系统(distributed control system, DCS)用的各种模拟量测量仪表、送DCS用的各种开关量测量仪表。
系统LAA共有5项功能,其中2项功能分别会导致机组停堆单通道脱扣和停机,判定为关键功能;另外3项功能判定为重要功能。按系统功能关键度等级最高者为本文系统的关键度,则LAA系统为关键系统。
系统LCU共有5项功能,其中5项功能均为重要功能,则LCU系统为重要系统。
(1)关键系统的设备关键度分级。LAA为关键系统,因此按照如表2所示详细分级过程开展设备关键度分析。以设备功能、故障模式分析为基础,逐步判断功能失效对系统功能、机组两个层面的影响,判断得到设备关键度。
(2)重要系统的设备关键度分级。LCU系统为重要系统,因此按照如表3所示快速分级过程开展设备关键度分析。以设备正常运行状态为基础,分析运行状态转换时产生的功能失效影响,直接判断出设备关键度。
基于每个设备正常运行状态,对照判断准则,确定设备工作频度高(H)、低(L),如表2表3所示。
根据每个设备在系统中所处的环境,对照判断准则,确定设备工作环境严酷(S)、良好(M),如表2表3所示。
按照如上方法完成了快堆所有系统的设备可靠性分级,分级结果中各设备关键度占比及其与压水堆的对比如表4所示。
钠冷快堆属于第四代机组,由于其固有安全特性,与二代压水堆相比减少了大量核岛专设安全系统,此特点也在设备分级结果CC1(占比0.36%)和CC2(占比3.12%)较低的占比中得到了体现。
由于快速分级过程不分析设备功能和失效模式、不判断显隐性失效,仅基于常用的功能状态进行失效影响分析、判定设备关键度,在实践中新方法相较于SRCM和AP-913方法可节省约1/3工作时间。对比表2表3并结合表1,如此分级的合理性、有效性如下。
(1)从界定的关键度判断准则来看,关键系统的失效后果与核安全密切相关,需进行严格的详细分析;重要系统往往存在可靠性冗余、失效后果与经济性相关,在资源约束条件下可进行简化的快速分析。
(2)从设备关键度判定的难易程度来看,重要系统的设备关键度判定,只面临两个选项:重要、一般,在不详细分析设备功能、失效模式等情况下,也容易准确判定设备关键度。而关键系统的设备关键度判定需要从3个选项(关键、重要、一般)中选择,准确判定的难度相对较大,需要详细的分析判断过程。
(3)核电机组通常会长时间处于稳定运行工况,相应的设备功能状态不会发生变化。因此,重要系统只对最常用的功能状态及其失效进行分析,切合实际、高效且准确。
提出了一种设备可靠性分级的新方法,其融合了相关方法的思想和优点,在核电工期紧张、人员运行经验不足的情形下,新方法设计的操作流程有助于相对快速和准确地完成分级工作。
利用该方法完成了示范快堆所有系统的设备可靠性分级,并已在示范快堆的运营生产中得到应用和检验,可以用于其他处于建设阶段核电工程的可靠性分级工作。
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2025年第25卷第14期
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doi: 10.12404/j.issn.1671-1815.2404697
  • 接收时间:2024-06-23
  • 首发时间:2025-07-09
  • 出版时间:2025-05-18
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  • 收稿日期:2024-06-23
  • 修回日期:2025-02-25
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    1. 海军工程大学核科学技术学院, 武汉 430033
    2. 武汉第二船舶设计研究所第十研究室, 武汉 430064
    3. 中核武汉核电运行技术股份有限公司维修中心, 武汉 430223
    4. 中核霞浦核电有限公司设备处, 宁德 355100

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*赵新文(1968—),男,汉族,河南信阳人,博士,教授。研究方向:核反应堆概率安全分析。E-mail:
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小菇科 Mycenaceae 2 12 5.74 丝盖伞属 Inocybe 5 2.39
多孔菌科 Polyporaceae 8 14 6.70 蜡蘑属 Laccaria 5 2.39
红菇科 Russulaceae 3 23 11.00 小皮伞属 Marasmius 6 2.87
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