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Nuclear power plants -- Instrumentation important to safety -- Radiation monitoring for accident and post-accident conditions -- Part 3: Equipment for continuous high range area gamma monitoring
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GB/T 12726.3-2013
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| GB/T 12726.3-1992 | English | 399 |
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Radiation monitoring equipment for accident and post-accident conditions in nuclear power plant Part three. High range area gamma radiation dose rate monitoring equipment for accident and post accident conditions
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GB/T 12726.3-1992
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Basic data | Standard ID | GB/T 12726.3-2013 (GB/T12726.3-2013) | | Description (Translated English) | Nuclear power plants -- Instrumentation important to safety -- Radiation monitoring for accident and post-accident conditions -- Part 3: Equipment for continuous high range area gamma monitoring | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F69 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 11,128 | | Older Standard (superseded by this standard) | GB/T 12726.3-1992 | | Quoted Standard | GB/T 12726.1-2013; GB/T 14054-2013; ISO 4037-1; ISO 4037-2; ISO 4037-3; ISO 4037-4; ISO 6980.1; ISO 6980.2; ISO 6980.3; ISO 8529-1; ISO 8529 -2; ISO 8529-3; IEC 60780; IEC 61226 | | Adopted Standard | IEC 60951-3-2009, IDT | | Regulation (derived from) | National Standards Bulletin No. 25 of 2013 | | Issuing agency(ies) | General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, Standardization Administration of the People's Republic of China | | Summary | This standard specifies the design principles and performance criteria after the nuclear power plant accident and the high range area �� continuous monitoring equipment. GB/T 12726. 1-2O13 gives the general requirements for the technical characteristics of |
GB/T 12726.3-2013: Nuclear power plants -- Instrumentation important to safety -- Radiation monitoring for accident and post-accident conditions -- Part 3: Equipment for continuous high range area gamma monitoring
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. Nuclear power plants Instrunmentation important to safety Radiation monitoring for accident and post-accident conditions Part 3. Equipment for continous high range area gamma monitoring
ICS 27.120.20
F69
National Standards of People's Republic of China
Replacing GB/T 12726.3-1992
Nuclear power plant safety important instrument
After the accident and radiation monitoring
Part 3. High range area γ continuous monitoring equipment
Part 3. Equipmentforcontinoushighrangeareagammamonitoring
(IEC 60951-3.2009, IDT)
Issued on. 2014-08-01 2013-12-17 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Table of Contents
Preface Ⅰ
Introduction Ⅱ
1 Scope 1
2 Normative references 1
3 Terms and definitions
4 Design Principle 2
4.1 Overview 2
4.2 Measuring range 2
4.3 Accuracy (relative error) 2
Position detector 2 4.4
4.5 Radiation Detector response 2
4.6 accident conditions relevant requirements 2
5 Functional Test 2
5.1 General Requirements 2
5.2 Reference Source 3
5.3 Performance Characteristics 3
1 4 energy response
Table 1 SAC/TC30/SC2/SC3 standard series Ⅳ
Supplementary Table 2 GB/T 12726.1-2013 test specified Additional Tests 5
Foreword
GB/T 12726 "after the nuclear power plant safety is important instruments accident and radiation monitoring" is divided into four parts.
--- Part 1. General requirements;
--- Part 2. gaseous effluents and ventilation equipment for continuous monitoring of radioactivity in the offline;
--- Part 3. High range area γ continuous monitoring equipment;
--- Part 4. Process flow tube or inner tube beside continuous radioactivity monitoring equipment.
This section GB/T Part of 312,726.
This section drafted in accordance with GB/T 1.1-2009 given rules.
This Part replaces GB/T 12726.3-1992 "after a nuclear power plant accident and the third part of the radiation monitoring equipment. High range area γ
Continuous monitoring equipment, "compared with the GB/T 12726.3-1992 main technical changes are as follows.
--- Standard name changed to "nuclear power plant safety important instrument for accident and post accident radiation monitoring - Part 3. High range area γ continuous
Monitoring equipment ";
--- "2 Normative references" to add some standard text in the standard reference;
--- "3 Terms and definitions" direct terms and definitions GB/T 12726.1-2013 given;
Title --- Chapter 4, "Design requirements" to "design principles", according to the contents of IEC 60951-3.2009 modification;
Title --- Chapter 5, "Technical characteristics and test methods" to "functional test", according to the contents of IEC 60951-3.2009 modification.
This section uses the translation method is equivalent to using IEC 60951-3. Radiation monitoring after 2009 "Instrumentation important to safety of nuclear power plants for accident and
Part 3. High range area γ continuous monitoring equipment. "
Consistency correspondence between this part of international documents and normative references of our files are as follows.
--- GB/T 12162 (all parts) for calibrating dosemeters and dose rate meters and for determining their response to X and γ reference radiations [ISO
4037 (all parts)];
--- GB/T 12164 (all parts) β reference radiation [ISO 6980 (all parts)];
--- GB/T 12727-2002 nuclear power plant safety systems of electrical equipment qualification (IEC 60780.1998, MOD);
--- GB/T 14055 (all parts) Reference neutron radiation [ISO 8529 (all parts)];
--- GB/T 15474-2010 nuclear power plant instrumentation and control functions important to safety classification (IEC 61226.2005, MOD);
For ease of use, this section made the following editorial changes.
--- Delete the original preface to the international standards;
--- Will be in "2 Normative references" have been corresponding national standards with international standards to our standards, increase in the "range 1"
Appearing in GB/T 14054-2013;
--- 5.1 in "these tests are shown in Table 1" to "see GB test under standard test conditions of/T 12726.1-2013 in
Table 2, the test with the impact of the amount of changes, see GB/T 12726.1-2013 in Table 3. See Additional tests conducted
Table 2. ";
--- 5.3.1 in the "sensitivity" to "respond";
--- Note to Table 2 into the table.
This part of the National Nuclear Instrument Standardization Technical Committee (SAC/TC30) and focal points.
This section drafted by. China Nuclear Power Institute.
The main drafters of this section. Chen Yue, Zeng Li, Li Gao, Li Kun.
GB/T 12726.3 first released in December 1992.
Introduction
a) standard technical background, major publications and organizations
This section focuses specifically on accident and after the accident radiation monitoring system in use.
The series of standards for user to a specific plant radiation monitoring system technical requirements, the manufacturer may be used in the series of standards
Determine the product characteristics required for the development of accident conditions of the system. Some detailed characteristics of the instrument, such as measuring range, in response to the energy and environmental conditions
Pieces shall be determined according to the specific application. In this case, the standard specifies only specific request, but does not claim itself will be described.
This section is important to safety after the accident radiation monitoring instruments in a standard series of standards. This series of standards consists of the following components.
--- GB/T 12726.1 important instrument for nuclear power plants accident and after the accident radiation monitoring - Part 1. General requirements
(GB/T 12726.1-2013, IEC 60951-1.2009, IDT)
--- GB/T 12726.2 important to safety of nuclear power plants after the accident and radiation monitoring instrumentation - Part 2. gaseous exhaust stream and pass
Wind Equipment for continuous monitoring of radioactivity in the offline (GB/T 12726.2-2013, IEC 60951-2.2009, IDT)
--- GB/T 12726.3 important to safety of nuclear power plants after the accident and radiation monitoring instruments - Part 3. High range area γ even
--- GB/T 12726.4 important to safety of nuclear power plants after the accident and radiation monitoring instrumentation - Part 4. inner tube or pipe flow process
Equipment for continuous monitoring radioactivity next (GB/T 12726.4-2013, IEC 60951-4.2009, IDT)
b) in the SAC/TC30/SC2/SC3 standard structure in the current standard status
GB/T 12726 series of standards is in the third level in SC2 standard hierarchy. GB/T 12726 series of standards for use in accident
And design and test conditions - radiation monitoring equipment to provide guidance after the accident. SC2 and SC3 other standards developed for use in normal operating
Radiation monitoring instruments under the conditions provided guidance. GB/T 7165 series of standards for the off-line continuous monitoring of radioactivity in gaseous effluents under normal conditions
It specifies the requirements for equipment. GB/T 10253 is a continuous off-line monitoring normal conditions of liquid radioactive effluents device specifies the requirements.
IEC 60768 for the continuous monitoring of the normal operation and anticipated operational occurrences within the process stream or a bypass pipe radioactive device specifies the requirements. most
After, ISO 2889 provides guidance for the gas and particle sampling. Table 1 shows the relationship between these different standards of radiation monitoring.
Table 1 SAC/TC30/SC2/SC3 standard series
Making organization ISO SC2 --- process and safety monitoring
After sampling circuit and a range of methods for accident and normal conditions and anticipated operational occurrences
SC3 --- radiation protection and
Effluent monitors
Zone sampling gases, particulates and
Iodine monitoring (offline)
ISO 2889
GB/T 12726.1 and
GB/T 12726.2
GB/T 7165 series of standards
Monitor with a liquid sample (from
line)
NA NA GB/T 10253
Without sampling (gaseous discharge
Flow, steam or liquid) process
Flow monitor (next to the pipe or tube)
Not applicable
GB/T 12726.1 and
GB/T 12726.4
IEC 60768 is not applicable
Regional monitoring does not apply
GB/T 12726.1 and
GB/T 12726.3
GB/T 14054
The central control system is not applicable IEC 61504 IEC 61559 series of standards
For details, see d SC2 series standard configuration).
c) The application of this series of standards and recommendations restrictions
Special attention in this series of standards does not establish additional functional requirements for the safety systems.
Relations d) SC2/SC3 standard describe the structure of the series and with other standards and other bodies (IAEA, ISO ) file
Top standard SC2 standard series is NB/T 20026. It is important for the implementation of nuclear power plant safety functions and instrumentation and control systems set up
Preparation of the provisions of the general requirements. NB/T 20026 standard series built SC2.
NB/T 20026 standard SC2 direct reference to the other, to the functional classification and grading systems, qualification, system isolation, Common Cause
Fault defense, computer-based software systems, hardware-based computer systems and control room design and other aspects. Should be considered in the second layer
Face direct reference to these standards and with the NB/T 20026 together as a reference document.
In the third level, not NB/T 20026 directly referenced SC2/SC3 standard relates to special equipment, technical methods, or specific living
Moving standard. In general, it refers to the second-level files These files can be its own reference.
Expanded technical report SC2/SC3 standard series, the fourth dimension is not part of the scope of standardization.
NB/T 20026 and basic safety publications have adopted similar representation formats.
Including the overall security architecture and life cycle system life cycle framework of IEC 61508 series of standards provide for the nuclear power plant sector
It describes the general requirements (IEC 61508.1, IEC 61508.2 and IEC 61508.4). Since the nuclear industry has to explain,
Comply NB/T 20026 will facilitate the IEC 61508 series of standards consistent with the requirements. In this framework, IEC 60880 nuclear applications sector
And IEC 62138 correspond to IEC 61508.3.
NB/T 20026 quality assurance (QA) aspects of reference GB/T 19000-2008, GB/T 19001-2008 and HAF003
(Corresponding to IAEA50-C-QA, IAEA50-C-QA now IAEAGS-R-3-substituted).
SC2 and consistent implementation of the standard series detailing the principles and basic safety considerations for nuclear safety and nuclear safety regulations guide nuclear power plant,
Especially HAF102 requirements, the establishment of nuclear power plant design and safety guide HAD102/14 relates to the safety of nuclear power plants and important instrument
Control systems related to safety requirements. SC2 standard uses of nuclear safety regulations and nuclear safety guidelines consistent terminology and definitions.
Nuclear power plant safety important instrument
After the accident and radiation monitoring
Part 3. High range area γ continuous monitoring equipment
1 Scope
This section GB/T 12726 specifies the design principles of the nuclear power plant after the accident and the high range area γ continuous monitoring equipment and performance
Guidelines.
GB/T 12726.1-2013 gives the technical characteristics of such equipment, test methods, radiation characteristics, electrical characteristics, mechanical properties and ring
General requirements for environmental characteristics, unless otherwise noted, these requirements apply to this section.
This section applies to accidents and post-accident monitoring high levels of γ radiation dose rate meter fixed. This section includes a measure isotropically
The amount of energy release in the air than the kinetic energy of 80keV ~ 7MeV γ radiation, the ambient dose equivalent amount of radiation or other devices. The device
Mainly used for security purposes nuclear power plants.
Emergency use portable instruments for continuous and determined work area during normal operation in the case of fixed radioactive radiation monitor in
GB/T 14054-2013 is given within the scope of.
2 Normative references
The following documents for the application of this document is essential. For dated references, only the dated version suitable for use herein
Member. For undated references, the latest edition (including any amendments) applies to this document.
Instrumentation important to safety after the accident and radiation monitoring - Part 1 GB/T 12726.1-2013 nuclear power plant. General requirements
(IEC 60951-1.2009, IDT)
GB/T 14054-2013 radiation protection instruments X and γ radiation energy 50keV ~ 7MeV fixed dose rate meter, newspaper
Warning assemblies and monitors (IEC 60532.2010, IDT)
ISO 4037 (all parts) for calibrating dosemeters and dose rate meters and for determining X and γ reference radiations for its response (Xand
gammareferenceradiationforcalibratingdosemetersanddoseratemetersandfordeterminingtheir
responseasafunctionofphotonenergy)
ISO 6980 (all parts) nuclear β reference radiation (Nuclearenergy-Referencebeta-particleradiation)
ISO 8529 (all parts) Reference neutron radiation (Referenceneutronradiations)
IEC 60780 Nuclear power plant safety systems of electrical equipment qualification (Nuclearpowerplants-Electricalequipment
ofthesafetysystem-Qualification)
IEC 61226 Nuclear power plant instrumentation and control systems important to safety instrumentation and control functions classification (Nuclearpowerplants-
Instrumentationandcontrolsystemsimportanttosafety-Classificationofinstrumentationand
controlfunctions)
3 Terms and Definitions
Terms and definitions GB/T 12726.1-2013 defined apply to this document.
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