GB/T 12789.1-2025 English PDFUS$299.00 · In stock
Delivery: <= 3 days. True-PDF full-copy in English will be manually translated and delivered via email. GB/T 12789.1-2025: Criteria for nuclear reactor instrumentation - Part 1: General principles Status: Valid GB/T 12789.1: Historical versions
Basic dataStandard ID: GB/T 12789.1-2025 (GB/T12789.1-2025)Description (Translated English): Criteria for nuclear reactor instrumentation - Part 1: General principles Sector / Industry: National Standard (Recommended) Classification of Chinese Standard: F69 Classification of International Standard: 27.120.10 Word Count Estimation: 14,144 Date of Issue: 2025-04-25 Date of Implementation: 2025-11-01 Older Standard (superseded by this standard): GB/T 12789.1-1991 Issuing agency(ies): State Administration for Market Regulation, China National Standardization Administration GB/T 12789.1-2025: Criteria for nuclear reactor instrumentation - Part 1: General principles---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 12789.1-1991 Nuclear Reactor Instrumentation Guidelines Part 1.General principles Released on 2025-04-25 2025-11-01 Implementation State Administration for Market Regulation The National Standardization Administration issued Table of contentsPreface 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 4 5.5 Calibration and testing of neutron fluence rate measuring instruments 5 6 Temperature measurement 5 6.1 General requirements 5 6.2 Fuel assembly temperature measurement 5 6.3 Moderator Temperature Measurement 5 6.4 Coolant temperature measurement 5 6.5 Temperature Measurements Important to Reactor Safety 6 6.6 Temperature protection instrument 6 7 Coolant Measurement 6 7.1 General requirements 6 7.2 Coolant flow measurement 6 7.3 Coolant pressure measurement 7 7.4 Coolant level measurement 7 7.5 Coolant Leakage Measurement 7 7.6 Coolant Purity Measurement 7 7.7 Coolant radioactivity measurement 7 8 Protection system 7 9 Instrument power source 8 9.1 General requirements 8 9.2 Reliable power system 8 10 Control facilities 8 10.1 General requirements 8 10.2 Technical requirements for functional design 8 11 Alarm device 9 11.1 General requirements 9 11.2 Alarm System Design 9ForewordThis 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 1 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 12789.1-1991 "Nuclear reactor instrumentation standards Part 1.General principles" and is compatible with GB/T 12789.1- Compared with.1991, in addition to structural adjustments and editorial changes, the main technical changes are as follows. --- Added terms and definitions (see Chapter 3); --- Changed the content of pulse counting instrument (see 5.3.4, 4.4.4 of the.1991 edition); --- Changed the content of fuel assembly temperature measurement (see 6.2, 5.3 of the.1991 edition); --- Changed the content of instrument power source (see Chapter 9, Chapter 8 of the.1991 edition); --- Changed the content of control facilities (see Chapter 10, Chapter 9 of the.1991 edition); --- Changed the content of alarm devices (see Chapter 11, Chapter 10 of the.1991 edition). 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., Jiangsu Nuclear Power Co., Ltd., Hainan Nuclear Power Co., Ltd., China National Nuclear Corporation Zhangzhou Energy Co., Ltd., Fujian Fuqing Nuclear Power Co., Ltd., China National Nuclear Corporation Operation and Maintenance Technology Co., Ltd. Company, University of Electronic Science and Technology of China, Institute of Nuclear Industry Standardization, and Nuclear and Safety Radiation Center of the Ministry of Ecology and Environment. The main drafters of this document are. Zhang Yun, Huang Youjun, Jiang Tianzhi, He Liang, Li Wenping, Xu Tao, Shen Feng, Zhang Fan, Duan Pengfei, Wang Gui, Fan Sui, Chen Peng, Li Tianyou, Jian Yifan, Tang Tao, Wang Shuai, Jiao Liling, Li Jiang, Liu Jingbin, Qiao Ning, Yang Yang, Luo Nanke, Li Wei, He Shaoqun, Zhang Wei, Zhang Malu, Deng Shiyi, Hong Shixin, Guo Tangwen, Zhang Qi, and Zhang Peiran. The previous versions of this document and the documents it replaces are as follows. ---First published in.1991 as GB/T 12789.1-1991; ---This is the first revision.IntroductionGB/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. The required special instruments and general principles of 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 1.General principles1 ScopeThis document specifies the general specifications of the special instruments and their applications necessary for the safe operation of pressurized water reactors, high temperature gas-cooled reactors, and liquid metal-cooled fast reactors. Requirements, including general requirements, neutron flux rate measurement, temperature measurement, coolant measurement, protection system, instrument power source, control facilities, alarm Requirements for devices, etc. This document is applicable to the design and implementation of instruments directly related to reactor safety and control, and is used as a reference for other reactor types.2 Normative referencesThe 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 13284 Nuclear power plant safety system design criteria GB/T 13630-2015 Nuclear power plant control room design3 Terms and definitionsThe terms and definitions defined in GB/T 4960.2 and GB/T 4960.6 apply to this document.4 General requirements4.1 The nuclear reactor operator shall be responsible for the safe operation of the reactor, but the reactor instrumentation should be designed to be easy to use throughout the reactor life. Safe operation under various credible working conditions. 4.2 The instrument design should enable operators to respond promptly to and fully evaluate the physical state and dynamic characteristics of the reactor and provide appropriate alarm to indicate abnormal conditions. 4.3 The safety classification of the instrument is determined by the following factors. a) the safety functions that the instrument is to perform; b) the consequences of failure to perform its safety functions; c) the possibility that the instrument is required to perform a safety function; d) The time or duration for which the instrument is required to perform a certain safety function after the occurrence of the assumed initiating event. 4.4 Considering the various natures of accidents, the complexity of core performance caused by over-irradiation of the core and the numerical methods used to estimate the impact of accidental events, The mathematical model may introduce unknown errors, and the use of a single parameter measurement generally does not provide adequate protection. Therefore, at least two independent parameters should be measured. To monitor some kind of accidental event and perform protection, one of the parameters should be measured directly. 4.5 The reactor control system and the reactor safety system should remain independent, and the failure of one system will not cause the malfunction of the other system. ......Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB/T 12789.1-2025_English be delivered?Answer: Upon your order, we will start to translate GB/T 12789.1-2025_English as soon as possible, and keep you informed of the progress. The lead time is typically 1 ~ 3 working days. The lengthier the document the longer the lead time.Question 2: Can I share the purchased PDF of GB/T 12789.1-2025_English with my colleagues?Answer: Yes. 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