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GB/T 12789.2-2025: Criteria for nuclear reactor instrumentation - Part 2: Pressurized water reactors
Status: Valid GB/T 12789.2: Evolution and historical versions
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| GB/T 12789.2-2025 | English | 299 |
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Criteria for nuclear reactor instrumentation - Part 2: Pressurized water reactors
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GB/T 12789.2-2025
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| GB/T 12789.2-1991 | English | 249 |
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Criteria for nuclear reactor instrumentation. Part 2: Pressurized water reactors
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GB/T 12789.2-1991
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Basic data | Standard ID | GB/T 12789.2-2025 (GB/T12789.2-2025) | | Description (Translated English) | Criteria for nuclear reactor instrumentation - Part 2: Pressurized water reactors | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F69 | | Classification of International Standard | 27.120.10 | | Word Count Estimation | 14,129 | | Date of Issue | 2025-04-25 | | Date of Implementation | 2025-11-01 | | Older Standard (superseded by this standard) | GB/T 12789.2-1991 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 12789.2-2025: Criteria for nuclear reactor instrumentation - Part 2: Pressurized water reactors
---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
ICS 27.120.10
CCSF69
National Standard of the People's Republic of China
Replaces GB/T 12789.2-1991
Nuclear Reactor Instrumentation Guidelines
Part 2.Pressurized water reactors
Released on 2025-04-25
2025-11-01 Implementation
State Administration for Market Regulation
The National Standardization Administration issued
Table of contents
Preface III
Introduction IV
1 Scope 1
2 Normative references 1
3 Terms and Definitions 1
4 General Requirements 1
5 Neutron Fluence Rate Measurement 2
5.1 General requirements 2
5.2 Neutron Detector 2
5.3 Neutron Fluence Rate Measuring Instrument 3
5.4 Neutron Fluence Rate Level-Related Alarms, Controls, and Shutdowns 3
5.5 Calibration and testing of neutron fluence rate measuring instruments 3
6 Temperature measurement 3
6.1 General requirements 3
6.2 Fuel assembly temperature measurement 3
6.3 Coolant temperature measurement 3
6.4 Temperature measurements important to reactor safety 4
6.5 Temperature protection instrument 4
6.6 Temperature display 4
7 Coolant Measurement 4
7.1 General requirements 4
7.2 Coolant flow measurement 4
7.3 Coolant pressure measurement 4
7.4 Coolant level measurement 5
7.5 Coolant Leakage Measurement 5
7.6 Coolant Purity Measurement 5
7.7 Reactivity Control 5
8 Protection system 5
8.1 General requirements 5
8.2 Emergency shutdown system 5
8.3 Special safety device drive system 6
8.4 Measurement of protection variables 6
9 Instrument power source 7
10 Control facilities 7
11 Alarm device 7
Foreword
This document is in accordance with the provisions of GB/T 1.1-2020 "Guidelines for standardization work Part 1.Structure and drafting rules for standardization documents"
Drafting.
This document is Part 2 of GB/T 12789 “Criteria for Nuclear Reactor Instrumentation”. GB/T 12789 has been published in the following parts.
--- Part 1.General principles;
--- Part 2.Pressurized water reactor;
--- Part 3.High temperature gas-cooled reactor;
--- Part 4.Liquid metal cooled fast reactor.
This document replaces GB/T 12789.2-1991 "Criteria for Instrumentation in Nuclear Reactors Part 2.Pressurized Water Reactors" and is compatible with GB/T 12789.2-
Compared with.1991, in addition to structural adjustments and editorial changes, the main technical changes are as follows.
--- Changed the description of the scope (see Chapter 1, Chapter 1 of the.1991 edition);
--- Added "Terms and Definitions" (see Chapter 3);
--- Changed the description of the reactor coolant circuit (see 4.2, 3.4 of the.1991 edition);
--- Added fission product monitoring instrumentation requirements (see 4.6);
--- Added parameter requirements for indicating the rate of change of neutron injection rate and correction requirements for the rate of change of neutron injection rate (see 5.1.2);
--- Added design requirements for power distribution monitoring using continuous measurement devices (see 5.1.3);
--- Added relevant requirements for passive starting (see 5.1.5);
--- Added the calibration and calibration methods of neutron fluence rate measuring instruments (see 5.3.3);
--- Added coolant flow measurement method (see 7.2.2);
--- Changed the description of the requirements for dedicated safety facilities (see 8.3, 7.2 of the.1991 edition);
--- Added the description of the dedicated safety facility actions of "starting main feedwater isolation" and "main steam isolation" (see 8.3.6 and 8.3.7).
Please note that some of the contents of this document may involve patents. The issuing organization of this document does not assume the responsibility for identifying patents.
This document was proposed and coordinated by the National Technical Committee for Standardization of Nuclear Instruments (SAC/TC30).
This document was drafted by. China Nuclear Power Research and Design Institute, China Nuclear Power Engineering Co., Ltd., China General Nuclear Power Engineering Co., Ltd., China National Nuclear Power
Operation Management Co., Ltd., Fujian Fuqing Nuclear Power Co., Ltd., Nuclear and Radiation Safety Center of the Ministry of Ecology and Environment, and Nuclear Industry Standardization Institute.
The main drafters of this document are. Xu Tao, Liu Danhui, He Liang, Qin Yue, Li Zhuoyue, Li Hongxia, Zhu Jialiang, Zhang Yun, Wang Hailin, Deng Zhiguang, Wu Qian,
Zhu Biwei, Xu Sijie, Wang Xuemei, Lü Xin, Huang Youjun, Jiang Tianzhi, Chen Peng, Liu Hongchun, Deng Shiyi, Guo Lin, Yang Zhen, Guan Yue, Huang Xianxuan, Liu Jingbin,
Qiao Ning, Jiao Liling, and Li Cang.
The previous versions of this document and the documents it replaces are as follows.
---First published in.1991 as GB/T 12789.2-1991;
---This is the first revision.
Introduction
GB/T 12789 "Guidelines for Nuclear Reactor Instrumentation" is intended to consist of four parts.
--- Part 1.General principles. The purpose is to specify the principles necessary for the safe operation of pressurized water reactors, high temperature gas-cooled reactors, and liquid metal-cooled fast reactors.
Required special instruments and general principles for their application.
--- Part 2.Pressurized water reactor. The purpose is to supplement Part 1 and specify the general requirements for pressurized water reactor type instrumentation and its application.
in principle.
--- Part 3.High temperature gas-cooled reactor. The purpose is to supplement Part 1 and specify the instrumentation and
General principles for its application.
--- Part 4.Liquid metal cooled fast reactor. The purpose is to supplement Part 1 and specify the fast reactor instrumentation and its application.
General principles.
Nuclear Reactor Instrumentation Guidelines
Part 2.Pressurized water reactors
1 Scope
This document specifies the general requirements for the special instruments and their application necessary for the safe operation of pressurized water reactors, including general requirements, neutron injection
Requirements for frequency measurement, temperature measurement, coolant measurement, protection systems, instrument power sources, control facilities, alarm devices, etc.
This document applies to the design and implementation of instrumentation directly related to reactor safety and control in pressurized water reactor types.
2 Normative references
The contents of the following documents constitute essential clauses of this document through normative references in this document.
For referenced documents without a date, only the version corresponding to that date applies to this document; for referenced documents without a date, the latest version (including all amendments) applies to
This document.
GB/T 4960.2 Nuclear Science and Technology Terminology Part 2.Fission Reactor
GB/T 4960.6 Nuclear Science and Technology Terminology Part 6.Nuclear Instrumentation
GB/T 12789.1-2025 Nuclear reactor instrumentation standards Part 1.General principles
GB/T 13284 Nuclear power plant safety system design criteria
3 Terms and definitions
The terms and definitions defined in GB/T 4960.2 and GB/T 4960.6 apply to this document.
4 General requirements
4.1 Pressurized water reactor nuclear reactor instruments shall meet the general requirements of GB/T 12789.1-2025.
4.2 Fuel cladding temperature is an important reactor parameter, but it is not measured directly. Instead, it is measured by measuring the temperature of the reactor coolant system.
The data are inferred from the temperature, pressure and flow rate as well as the reactor power and spatial distribution.
The feedback is demonstrated based on nuclear measurements, thermal measurements, control rod positions, and measurements related to power level and other parameters that reflect the reactor status.
The spatial distribution of stack power and power density should be within the allowable range.
Measurements indicating a significant imbalance between reactor power and required power can be used to provide protection functions. These measurements include
The volume change of the reactor coolant system is obtained based on the pressurizer liquid level measurement. In addition, the imbalance between the reactor power and the required power
Conditions can also be measured and used as protection functions. These conditions include turbine shutdown and loss of heat sink (low water level in steam generator
or low feedwater flow rate).
Rely on safety valve action or reactor power reduction to prevent overpressure of the reactor coolant pressure boundary.
Rupture of the reactor coolant pressure boundary that exceeds the water replenishment system capacity will cause the reactor coolant system pressure to decrease and the pressurizer water level to increase.
The containment barrier is used to withstand the pressure, temperature and other impacts caused by the rupture of the reactor coolant circuit.
The containment should be equipped with measuring devices that can activate the protection system to ensure the integrity of the containment after an accident.
Although direct measurement of barrier integrity is usually not possible, process parameters should be measured that characterize the following conditions.
a) Conditions that cause overstress in one of the three barriers (fuel cladding, reactor coolant pressure boundary, containment);
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