GB/T 13632.2-2006 监督压水堆堆芯充分冷却的测量要求 第2部分：冷停堆期间监测仪表的要求

ICS27.120

F82

中华人民共和国国家标准

GB/T13632.2-2006

监督压水堆堆芯充分冷却的测量要求

第2部分:冷停堆期间监测仪表的要求

Measurementsformonitoringadequatecoolingwithinthecore

ofpressurizedlightwaterreactors-

Part2:Instrumentationrequirementsduringcoldshutdown

(IEC62117:1999,Nuclearreactorinstrumentation-Pressurizedlight

waterreactors(PWR)-Monitoringadequatecoolingwithinthecore

duringcoldshutdown,MOD)

2006-03-02发布2006-08-01实施

中华人民共和国国家质量监督检验检疫总局发布

中国国家标准化管理委员会

GB/T13632.2-2006

目次

一

9}0IAA

范围···············································································································……1

2规范性引用文件·················································································.……1

3术语和定义······································································································……1

4运行状态···············································，························································……2

4.1概述············································································································……2

4.2冷停堆维修运行················································，·······························.·……3

冷停堆换料运行············································································..··········……3

测量方法.·3

5.1概述·······························，···························，·············································……3

5.2RPV水位测量·························，········································，···········，·················……3

5.3RPV出口管水位测量4

5.4堆芯出口温度测量.·4

6仪表要求·····································································································……5

6.1一般要求·································，····································································……5

6.2差压测量······································································································……5

6.3温差传感器······································，····························································……7

6.4超声波水位测量················，·····························································..··..·········……7

6.5温度传感器·············································，·····················································……7

7数据处理··············，··················7

8信息的提供·····································································································……7

8.1功能要求·····································································································……7

8.2人因考虑·····················8

9验证和校准······································································································……8

10在役试验和维护········································································.···············.·……8

I1质量合格鉴定·································································································……8

12文件资料········································································································……8

附录A(资料性附录)压水堆(PWR)冷停堆期间丧失堆芯冷却的事故31

附录B(资料性附录)核电厂运行状态·················……’二‘””””“’‘41

GB/T13632.2-2006

.山J曰.日‘~

月U舌

本部分为GB/T13632《监督压水堆堆芯充分冷却的测量要求》的第2部分

本部分修改采用IEC62117:1999核《反应堆仪表压水堆(PWR)监测冷停堆期间堆芯充分冷却

要求))(英文版)。

本部分根据IEC62117;1999重新起草。

考虑到我国核电厂的现状，在采用IEC62117:1999时，本部分做了少量技术性修改:

a)删去"，2规范性引用文件”中的IEC60050(393):1996((国际电工词典(IEV)393章:核仪器仪

表:物理现象和基本概念》;

b)删去第3章的缩写:ALARA(合理可行尽量低),DBA(设计基准事故),RCS(反应堆冷却剂系

统),RPV(反应堆压力容器);

c)删去5.1.2中有关沸水堆的内容(见IEC61343:1996《核反应堆仪表沸水堆(BWR)在反

应堆容器内监测堆芯充分冷却的要求))};

d)将6.1.2,6.1.4和6.4.4中RPV出口管道水位测量应给出的“模拟显示”，改为“显示(模拟或

数字式)”;

e)将6.2.1引用标准IEC60770-1:1999工《业过程控制系统用变换器第一部分:性能评价方

法》改为HAD102/14(1988)《核电厂安全有关仪表和控制系统》;

f)第8章增加一条"8.2人因考虑”，增加“显示信息和仪表的设计详见EJ/T759.2,";

9)第9章增加引用标准“EJ/T626-1992《核电厂电气、仪表和控制设备的安装、检查和试验要

求》”。

为便于使用，对于IEC62117,1999本部分还做了下列编辑性修改:

a)将IEC62117的引言和“1范围和目的”中对标准的说明改为本部分的引言;

b)删除IEC62117的前言;

c)将IEC62117引用的规范性文件((IEC标准和IAEA规定)改为对应的我国标准和法规。

本部分符合HAF103核《动力厂运行安全规定》(2004)第5.3.2条.，’二。必须对堆芯状况进行监测，

必要时对装、换料大纲进行复查和修改。…”的规定，满足HAD103/08《核电厂维修》(1993)的有关

要求。

与本部分有关的标准是GB/T13632-1992《监督压水堆堆芯充分冷却的测量要求》，该标准等同

采用IEC60911,1987((监督压水堆堆芯充分冷却的测量要求))(英文版)，本部分是对GB/T13632-

1992的第I次补充，说明冷停堆期间堆芯充分冷却的要求，考虑了冷停堆期间为了维修将反应堆压力

容器内水位降低的工况下对仪表的具体要求，以保证堆芯充分冷却。这两个标准应结合使用以满足冷

停堆期间堆芯充分冷却的要求。

本部分的附录A和附录B是资料性附录

本部分由中国核工业集团公司提出

本部分由全国核仪器仪表标准化技术委员会归口。

本部分起草单位:核工业标准化研究所

本部分主要起草人:牛祝年、张京长

GB/T13632.2-2006

引言

IEC60911:1987((Measurementsformonitoringadequatecoolingwithinthecoreofpressurized

lightwaterreactors》规定了监测压水堆堆芯充分冷却的一般要求，但没有规定具体要求。各国在役压

水堆核电厂在冷停堆期间已经发生的事故表明，现有的监测系统虽然符合IEC60911:1987的要求，但

不能充分满足冷停堆期间的要求且易发生故障

因此国际电工委员会(IEC)制定了IEC60911:1987的补充标准IEC62117:1999((Nuclearreactor

instrumentation-pressurizedlightwaterreactors(PWR)-monitoringadequatecoolingwithinthecore

duringcoldshutdown))。本部分修改采用IEC62117:1999作为GB/T13632-1992(idtIEC60911:

1987)的第一次补充，目的是在冷停堆期间为了维修将反应堆压力容器内水位降低的工况下，规定对仪

表的具体要求以保证堆芯充分冷却。

只要流过堆芯的冷却剂流量足以排出堆芯热量就能实现堆芯的充分冷却。冷停堆期间是使用余热

排出系统(RHRS)强迫循环来提供堆芯冷却的。但在反应堆冷却剂温度低于1000C(212下)的停堆工

况下，为了维修将反应堆压力容器(RPV)内水位降低时强迫循环可能停止，堆芯就有可能过热，此时用

于堆芯冷却监测的仪表应起作用，本部分描述需要这些监测仪表起作用的情况，给出适用于下述情况的

多样性原则、适宜的装置及其要求:

a)运行工况;

b)安装;

c)操纵员显示器;

d)试验、校准和维修;

e)设备质量鉴定;

f)文件资料。

本部分也描述监测仪表在核电厂功率运行期间的典型应用。在超设计基准事故工况期间，堆芯冷

却监测的要求不属于本部分的范围。

本部分附录A选择国外PWR上已经出现过的一些事件，说明水位测量不可靠可能导致冷却剂循

环中断和堆芯过热，设计堆芯冷却监测仪表时应考虑这类工况。为了证实通过RPV的冷却剂温度和

流量足以带走堆芯产生的热量，应向核电厂操纵员提供可靠的信息，这类信息包括从堆芯到余热排出系

统(RHRS)循环冷却剂所用的RPV出口管道的水位监测、冷却剂温度和流量的监测。

GB/T13632.2-2006

监督压水堆堆芯充分冷却的测量要求

第2部分:冷停堆期间监测仪表的要求

范围

本部分规定了冷停堆期间堆芯充分冷却监测仪表的要求。

本部分适用于设计或改造配置类似于图1和图2所示的压水堆(以下简称PWR)时堆芯冷却监测

仪表的设计。

2规范性引用文件

下列文件中的条款通过本部分的引用而成为本部分的条款。凡是注日期的引用文件，其随后所有

的修改单(不包括勘误的内容)或修订版均不适用于本部分，然而，鼓励根据本部分达成协议的各方研究

是否可使用这些文件的最新版本。凡是不注日期的引用文件，其最新版本适用于本部分。

GB/T7166核动力堆堆芯或堆主包壳内温度的测量特性和测试方法(GB/T7166-1987,egv

IEC60737:1982)

GB/T12727核电厂安全