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GB/T 12726.2-2013: Nuclear power plants -- Instrumentation important to safety -- Radiation monitoring for accident and post-accident conditions -- Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air
Status: Valid GB/T 12726.2: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB/T 12726.2-2013 | English | 274 |
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Nuclear power plants -- Instrumentation important to safety -- Radiation monitoring for accident and post-accident conditions -- Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air
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GB/T 12726.2-2013
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| GB/T 12726.2-1991 | English | 479 |
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Radiation monitoring equipment for accident and post-accident conditions in nuclear power plants—Part 2: Specific requirements for equipment for continuously mo-nitoring radioactive noble gasses in gaseous effluents
| Obsolete |
GB/T 12726.2-1991
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PDF similar to GB/T 12726.2-2013
Basic data | Standard ID | GB/T 12726.2-2013 (GB/T12726.2-2013) | | Description (Translated English) | Nuclear power plants -- Instrumentation important to safety -- Radiation monitoring for accident and post-accident conditions -- Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F69 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 14,182 | | Older Standard (superseded by this standard) | GB/T 12726.2-1991; GB/T 12726.5-1997 | | Quoted Standard | GB/T 12726.1-2013; ISO 2889-2010; IEC 61229 | | Adopted Standard | IEC 60951-2-2009, 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 nuclear power plant accident and gaseous effluents and ventilation equipment for continuous monitoring of radioactivity in the offline general design principles and performance requirements. GB/T 12726. 1-2013 specifies the tec | GB/T 12726.2-2013: Nuclear power plants -- Instrumentation important to safety -- Radiation monitoring for accident and post-accident conditions -- Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air
---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.
. Nuclear power plants Instrumentation important to safety Radiation monitoring for accident and post-accident conditions Part 2. Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air
ICS 27.120.20
F69
National Standards of People's Republic of China
Replacing GB/T 12726.2-1991, GB/T 12726.5-1997
Nuclear power plant safety important instrument for accident and post accident
Radiation monitoring - Part 2. gaseous effluents and
Ventilation Equipment for continuously monitoring radioactivity offline
Part 2. Equipmentforcontinuousoff-linemonitoringof
(IEC 60951-2.2009, 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 the basic requirements relating to the function 2
4.3 sampling device 2
5 Function Test 4
5.1 Overview 4
5.2 Reference Source 4
5.3 Performance characteristics. a response to other radioactive gases or particles 4
Test 5.4 Characteristics of air circuit 5
Table 1 SAC/TC30/SC2/SC3 standard series Ⅱ
Supplementary Table 2 GB/T 12726.1-2013 specified tests Additional tests 8
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 212,726.
This section drafted in accordance with GB/T 1.1-2009 given rules.
This Part replaces GB/T 12726.2-1991 "after the nuclear power plant accident and radiation monitoring equipment Part II. gaseous effluents
Specific requirements for radioactive noble gas continuous monitoring equipment "and GB/T 12726.5-1997" after the nuclear power plant accident and radiation monitoring provided
Preparation Part V. air radioactivity monitoring equipment. " This portion of the GB/T 12726.2-1991 and GB/T 12726.5-1997 compared
The main technical changes are as follows.
--- Added two normative references, respectively IEC 61226 "important nuclear power plant safety instrumentation and control systems and instrumentation
Control classification ", ISO 2889.2010" Nuclear Facilities chimneys and ventilation duct sampling airborne radioactive material ";
--- Sampling device is designed taking into account the requirements of ISO 2889;
--- Sampling loop and material consideration of the requirements for gas-proof and anti-virus or corrosive gases;
--- Increasing the material requirements (for example, consider sampling lines and structural materials in aerosol particles and iodine sampling circuit loss as possible
Low energy);
--- This section only lists the additional tests, a pilot project under standard test conditions and the amount of change impact test
Test items are given in GB/T 12726.1-2013 in;
--- This part of the technical requirements and test methods were revised accordingly.
This section uses the translation method is equivalent to using IEC 60951-2. Radiation monitoring after 2009 "Instrumentation important to safety of nuclear power plants for accident and
Part 2. gaseous effluents and ventilation equipment for continuous monitoring of radioactivity offline. "
Consistency correspondence with international standards in this part of the country cited the following documents.
--- GB/T 15474-2010 nuclear power plant instrumentation and control functions important to safety classification (IEC 61226.2005, MOD).
This part made the following editorial changes.
--- Delete foreword international standards;
--- According to Chinese customs for some formatting has been modified (for example. Note plus behind ".", followed by a series Item Description will be. ""
Replaced by ";");
--- Use the decimal symbol instead of the international standard decimal symbol ",". ",";
--- Will be in "2 Normative references" have been corresponding national standards with international standards to national standards, GB/T 12726.1-
2013 "after the nuclear power plant safety is important instruments accident and radiation monitoring - Part 1. General requirements" instead of IEC 60951-1.
2009; ISO 2889 era is wrong to number 2009 2010;
--- Preserve the contents of the currently used only in voltage and frequency of the AC power supply, remove the power supply frequency of 57Hz ~ 61Hz
Claim;
--- Table 2 in the first row "5.4.1" in error, to "5.3."
This part of the National Nuclear Instrument Standardization Technical Committee (SAC/TC30) and focal points.
This section drafted by. China Nuclear Power Engineering Co., Ltd.
The main drafters of this section. Wang Yong Qin Wen Chao, Ding Shihai, Yang Guangli.
GB/T 12726.2 first released in September 1991, GB/T 12726.5 in June 1997 was first released, this revision will
GB/T 12726.2-1991 and GB/T 12726.5-1997 integration.
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.
IEC 61508 series of standards including the overall security architecture and life cycle system life cycle provides a general framework for the nuclear power sector
Description of requirements (IEC 61508.1, IEC 61508.2 and IEC 61508.4). Since the nuclear industry has to explain, in line with
NB/T 20026 will facilitate the IEC 61508 series of standards consistent with the requirements. In this framework, nuclear applications sector and IEC 60880
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 for accident and post accident
Radiation monitoring - Part 2. gaseous effluents and
Ventilation Equipment for continuously monitoring radioactivity offline
1 Scope
This section GB/T 12726 specifies the gaseous discharge after the nuclear power plant accident and flow and ventilation equipment for continuous monitoring of radioactivity offline
The general principles for design and performance requirements.
GB/T 12726.1-2013 specifies the technical characteristics of the equipment, test methods, radiation characteristics, electrical characteristics, mechanical characteristics and particular environmental
Sex. Unless otherwise noted, these requirements apply to this section.
This section applies to.
--- Inert gas activity monitor, the gaseous emissions at the point for measuring the accident and the conditions of the apparatus of radioactive effluents
Time change volume activity of inert gas, and with the volume of activity. The monitor can also be used to determine the timing of the idle period
Total emissions of radioactive gases.
--- Inert gases, aerosols and monitor specific nuclide (usually refers to different forms of a particular radionuclide iodine include. inorganic iodine, organic iodine gas
Sol iodine species), the device used to measure the air or gas ventilation systems (control room ventilation, reactor leak collection, Reactor
Pit ventilation, ventilation exhaust fuel processing plant, reactor building ventilation exhaust purification) of radioactive volume of activity, and exploration
Any significant increase of radioactivity measured during and after the accident in the accident.
This section applies only to off-line continuous monitoring equipment that is suitable for those discharged from the total gaseous stream flow or ventilation ducts removed part of the Generation
Table of the sample sent to a remote location (through the sampling device) detector and then measuring their equipment. This section does not apply to those detectors straight
Then installed in ventilation ducts or gaseous effluents stream, or installed near the discharge flow or ventilation airflow monitor device, such monitors
Belonging to GB/T 12726.4 of the scope of application.
Complete exhaust stream monitoring programs necessary samples for laboratory analysis is not within the scope of this section.
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)
ISO 2889.2010 Nuclear facilities chimneys and ventilation duct sampling airborne radioactive material (Samplingairborneradioactive
materialsfromthestacksandductsofnuclearfacilities)
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.
4 Design Principles
4.1 Overview
This section applies to all types of equipment in addition to the need to meet the requirements of this part, it must also meet the GB/T 12726.1-2013 provisions in general
Requirements, unless otherwise indicated.
4.2 Basic requirements and related functions
Gaseous effluents and ventilation equipment for continuous monitoring of radioactivity in the offline generally used to measure the radioactivity of nuclear engineering plant, such as the reactor building or
Fuel processing plant chimney ventilation ducts and activity levels gases path. According to the functional requirements, the device can also be used to measure the discharge
Radioactivity into the environment, to detect and identify security barrier (such as. containers, pipes) leaks, as well as provide any information or cause to live
Useful information about the release of the plant status.
Radioactive emissions to the environment should theoretically be fully measured, but because of effluents released from halogen and particulate activity during an accident
More complex measurements, monitoring is generally considered only an inert gas is sufficient. Thus, the monitor should have detected and measured inert gaseous effluents
The ability of the gas activity, such inert gas comprises an inert gas to reach equilibrium just mixed fission products to decay 10d old mixture. can
You can require multiple devices to cover the effective range of the measurement required.
Since the measurement is transmitted to a remote for gaseous effluents and ventilation samples continuously, so the detection and measurement devices should be installed
In easily accessible places, where the environmental conditions should be consistent with the provisions of this part of the equipment design extreme conditions. This requirement also applies to the required dimension
Active parts protected sampling device (pump, flow control instruments).
Other portions (sampling nozzle, transfer line) sampling device may be designed and installed in harsh environments. In this case, e.g.
If the monitor is classified according to IEC 61226, which is part of the monitor should be classified as the same category. If you need to identify, located in harsh environments
This part should be part of the sampling device in accordance with those specific environmental conditions environmental qualification.
If required, the system should be displayed at a temperature and pressure conditions at the sampling point and the measured volume of the activity related to values, but to be used by the manufacturer
And users agreed. If the measuring device calibration conditions and internal conditions are different, manufacturers and users should also agree on how to correct the measurement.
4.3 sampling device
4.3.1 Overview
Design of sampling device should refer to ISO 2889.2010 and meet the GB/T 12726.1-2013 the general requirements.
Sampling device generally includes one or more components and functional units.
--- Sampling and exhaust pipes;
--- Gas treatment apparatus (e.g. gas cooling means preventing or indoor condensation gas measurement with a device for removing condensate reheating means,
In order to remove the residual gas in the collection device with an external blow Importers wash pipe connection connecting pipe);
--- Measuring chamber;
--- Airborne particulate collection device.
● Aerosol Monitors aerosol filtration unit (filter with fixed or filter);
● Only for iodine and noble gas monitors inlet dust filter;
● iodine monitors iodine zeolite or activated carbon filters or filter cartridges (filter replacement device or a fixed filter);
--- Environmental γ radiation shielding means and/or compensation device;
--- Separate air pump or central pumping station;
--- Air flow measurement and/or control devices;
Pressure, temperature or humidity measurement and/or control unit (depending on the sampling conditions).
4.3.2 Measurement Technology Requirements
According to the measured nuclides respond air or gas filter to remove radioactive particles and iodine or incorporated volume is known and constant capacity
Device. In the latter case, the measuring chamber shall be air flow through type, and should be given its volume and pressure, as well as ease of maintenance or
Change detector, which should be easily disassembled, and should ensure that the detector can be accurately mounted on repeating geometrical position.
When the pressure-sensitive measurement techniques, should have the pressure measurements. Instrument calibration should take into account the actual operating pressure conditions as appropriate
Amendments. Sampling means acceptable change in pressure and pressure specified by the manufacturer. Should be carefully considered to ensure that the ends of the inlet filter
Pressure drop on the measurement chamber pressure is very small.
When measuring the flow of sensitive technology should provide flow measurement devices. Instrument calibration should be considered the actual operating pressure and temperature into
Row appropriate amendments. Should consider regulating the flow volume measurement means. It is also desirable to provide a flow control device, the flow of the apparatus
The adjustment range is sufficient to withstand changes in air pump can be used with any of the intrinsic properties of the filter. It should be based on the effects of different traffic measurement
Value amendment.
If necessary, measure atmospheric humidity to control the adjustment means in order to avoid condensate in the pipeline and the monitor. When the relative humidity is over
Crossing the manufacturer's specified value, it should provide an alarm signal.
These tests should be applied to all of the response depends on the traffic flow through the monitoring device known sampling and detection means.
When the device is not sensitive to changes in flow rate, but still need to meet the functional requirements of the sample flow, then shall the manufacturer and user
Agreement reached between the simple fluid circuit test and any flow alarm test.
When the device is sensitive to changes in flow rate and the sample flow with the discharge flow variations, it should be agreed between manufacturer and user the appropriate test.
5.4.2 monitor sampling efficiency
5.4.2.1 Overview
Compared to a particle collection efficiency for each given particle size, the monitor entry and collection filter between collection efficiency provided by the manufacturer,
It should not differ more than 10%. If the manufacturer and the user agrees, the actual test by particle simulation test instead.
5.4.2.2 particle size
In diameter and size range of collection efficiency measurement sampling system used by the particles, by the manufacturer and user agreement, for example. root
According to the diameter of the aerosol particles being monitored, given collection efficiency filter media for different sizes of particles and the like.
5.4.2.3 aerosol type
For aerosol collection efficiency tests There are several different types, such as.
--- Fluorescent tracer particles containing non-radioactive aerosols;
--- Non-radioactive aerosol by a latex or polystyrene spheres constituted;
--- Radioactive aerosol.
5.4.2.4 Test Method
It shall have the right by a median aerodynamic diameter of particles injected into the sampling line inlet air samples collected pipeline efficiency test
Experience. Particle size distribution may be more decentralized system have smaller geometric standard deviation. Sampling device should be under standard test conditions (flow rate)
jobs.
After sampling device is closed, shall determine the amount of aerosols collected on the sampling media. It should also determine the inlet gas monitor available
Sol total. This amount can be measured independently of the amount of aerosol sampling obtained or determined by the following.
--- On the inner surface of the inlet pipe and the amount of aerosols collected on other air circuit upstream media surface collected;
--- Amount of aerosol collected downstream of the collecting medium.
5.4.2.5 collection efficiency is determined
Monitor the collection efficiency (Em) shall formula (1).
Em =
GM
CT ×
100% (1)
Where.
CM --- amount deposited on the collector medium;
CT --- total aerosol.
If feasible, it is recommended to use another method to determine the total amount of aerosol CT as a means of obtaining verification value. Such methods include
Through a variety of equipment and measurement techniques (such as spectrophotometers, particle analyzer and a reference sample, etc.) into the device measuring aerosol concentrations.
If the total amount of material from the inside of the total aerosol sample collected to determine the monitor, then the total amount of aerosol CT (activity, quality or micro
Grains) by equation (2) gives.
CT = CM CU CD (2)
Where.
CU --- the amount collected from the upper reaches of the medium air circuit surface collected;
CD --- the amount collected in the collection medium downstream.
5.4.3 feelings of gas or particle retention
5.4.3.1 Overview
Inert gases or particles remain in the air circuit may affect the measured results. Therefore, to prevent such retention, factory design empty
Gas loop should be a reasonable choice of materials and structures.
If the manufacturer and the user agreed to instead of the actual test through simulation tests.
5.4.3.2 Requirements
The volume of activity greater than 10 times the decision threshold for injecting inert gas into the monitor. After injection of the monitor and clean air flushing, gas
Retention sensitivity test indicated value should be less than 1% of the maximum reading of the results.
A certain concentration of particles injected into the monitor. After injection of the monitor and clean air flushing, feelings of particle retention test finger
Indication should be less than 5% of the maximum reading of the results.
Test Method 5.4.3.3 inert gas
During the test, the device will require the design of the chemical form of measurement, which is equal to about 10 times the volume of activity determination threshold inert gas injection probe
Measuring device, and at least 10 times the response time of the device in the device.
Of the device does not capture system containing the gas to form a closed loop system, and inject sufficient volume of activity in this system
An inert gas is equal to 1000 times the decision thresho...
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