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GB 4075-2009: Sealed radioactive sources -- General requirements and classification
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Basic data | Standard ID | GB 4075-2009 (GB4075-2009) | | Description (Translated English) | Sealed radioactive sources -- General requirements and classification | | Sector / Industry | National Standard | | Classification of Chinese Standard | F70 | | Classification of International Standard | 13.280 | | Word Count Estimation | 20,288 | | Date of Issue | 2009-03-13 | | Date of Implementation | 2010-03-01 | | Older Standard (superseded by this standard) | GB 4075-2003 | | Quoted Standard | GB 15849-1995; GB/T 19001-2000 | | Adopted Standard | ISO 2919-1999, MOD | | Regulation (derived from) | Announcement of Newly Approved National Standards No. 3, 2009 (No. 143 overall) | | 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 Chinese standard relates to sealed radioactive sources based grading system, and the source of performance requirements, test methods, marking and certificates were required. This standard is a sealed radioactive source to provide an evaluation of their products in use, a series of safety tests, but also for users to choose the type of radioactive sources to meet the requirements of particular concern is to prevent leakage of radioactive material caused by exposure to ionizing radiation select the source type places can help. This standard also provides guidance for the management sector. This standard does not by source design, manufacturing methods or emit radiation method of grading scale, this standard does not include nuclear reactor radioactive substances (including sealed sources) and fuel components. | GB 4075-2009: Sealed radioactive sources -- General requirements and classification---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.
Sealed radioactive sources.General requirements and classification
ICS 13.280
F70
National Standards of People's Republic of China
Replacing GB 4075-2003
General requirements for sealed radioactive sources and classification
(ISO 2919.1999, Radiationprotection-Sealedradioactivesources-
Generalrequirementsandclassification, MOD)
Published 2009-03-13
2010-03-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China issued
Table of Contents
Introduction Ⅲ
1 Scope 1
2 Normative References 1
Terms and definitions 1 3
4 representation grading and 2
4 5 activity level requirements
5 6 Performance Requirements
6 7 test methods
8 9 Source Identification
9 Source Certificate 10
10 Quality Assurance 10
Annex A (normative) toxic radionuclides packet 11
Annex B (normative) Example 13 sealed radioactive source certificates
Annex C (informative) general requirements of harsh environmental conditions 14
Annex D (informative) Additional test 15
Reference 16
Foreword
This standard Chapter 4, Section 5, Chapter 6, Section 8, Chapter 9 and Chapter 10 are mandatory, the rest are recommended.
This modification uses the standard ISO 2919.1999 "General requirements and classification sealed radioactive sources."
This standard and ISO 2919.1999 there is a technical difference compared.
--- deleted the foreword and introduction of international standards;
--- 4.1 in hierarchical representation to be modified according to the actual situation in China;
Chapter 8. --- increase the source coding.
Instead of the standard GB 4075-2003 "General requirements and classification of sealed radioactive sources." This standard and GB 4075-2003 compared to the main
It has the following changes.
a) All the original standard "GB/T 15849-1995" to "GB 15849-1995";
b) increasing the normative references ring [2004] 118 "Radioactive Sources Encoding Rules";
c) an increase in the Standard GB 4075 after 4.1 hierarchical representation, modified to GB 4075/××××/C (or E) ×××
×× (×);
d) increasing the amount of pollution in the test requirements pollution 6.1;
e) The 7.6.1.1 in b), c item) were combined, to modify the height of the striker (6.0 ± 0.2) mm, the diameter of (3.0 ± 0.1) mm;
f) an increase in the radiation source encoded source identification Chapter 8, chapter 9 and Appendix B certificate source;
g) Remove Chapter 8, the expression "(see ISO 361)" and the "cladding should be identified prior to testing sealed sources";
h) the bending test parameters of FIG. 1 is modified;
i) the expression of the modified certificate Appendix B;
j) The Appendix D file references are incorporated normative documents listed;
k) the reference upgraded version 1 to version 2005;
l) for some of the text to be modified to make the technology more explicit meaning.
This standard appendix A, to Appendix B, appendix C, Appendix D are informative annex.
This standard by the National Standardization Technical Committee of Nuclear Energy.
Drafted by. China Institute of Atomic Energy.
The main drafters of this standard. Duan Limin, Gong Lingling.
This standard was first published on December 24, 1983, the first amendment March 24, 2003.
General requirements for sealed radioactive sources and classification
Range 1
This standard is established to test the performance of a sealed radioactive based classification system, and the source of the performance requirements, test methods, and identification certificates
Etc. makes provision.
This standard provides a series of tests evaluated the safety of the product in use of sealed radioactive sources producer, but also for the user is selected from
Select the type of radioactive sources to meet the requirements of particular concern is to prevent the site selection due to leakage of radioactive material caused by exposure to ionizing radiation
The type of radioactive sources can provide help. This standard also provides guidance for the management department.
These tests are divided into several groups, e.g., including exposure to an abnormally high temperature and low temperature test and various mechanical tests. Each test is not applicable to
The same degree of stringency. Whether the test result by, depending on the contents of sealed radioactive leaks.
Note 1. The leak test methods see GB 15849-1995.
Table 4 shows the level of each application and testing is recommended primarily in the typical use of sealed radioactive sources. Broadly speaking, these tests are
Minimum requirements for a variety of uses, especially when used in some harsh conditions (see Appendix C) factors to be considered are listed in 4.2.
Note 2. The producer and inspection body shall GB/T 19001-2000, respectively, to develop quality assurance programs.
The method according to the present standard does not scale source design, manufacturing method of grading emit radiation, this standard is not included within the nuclear reactor radioactive
Mass (including sealed sources) and the fuel element.
2 Normative references
Terms of the following documents become provisions of this standard by reference in this standard. For dated reference documents, all later
Amendments (not including errata content) or revisions do not apply to this standard, however, encourage the parties to agreements based on this standard
Whether the latest versions of these documents. For undated references, the latest version applies to this standard.
Leakage test methods GB 15849-1995 sealed radioactive sources (eqv ISO 9978.1992)
GB/T 19001-2000 quality management system requirements (idt ISO 9001.2000)
"Radioactive Sources Encoding Rules" (cycloalkyl [2004] No. 118)
3 Terms and Definitions
This standard uses the following terms and definitions.
3.1
To prevent leakage of radioactive material in a protective shell.
3.2
Some reproductions of sealed radioactive sources, with the sealing structure and material identical to that of the cladding radioactive sources, but the source with radioactive material in the core
Physical and chemical properties similar to the material in place.
3.3
In determining the geometry, the number of particles sealed radioactive source of ionizing radiation and/or the number of photons emitted per unit time.
Note. The term preferably represents a radiation fluence rate.
3.4
Radioactive material from escaping into the environment of sealed radioactive sources.
3.5
The term encapsulated sealed radioactive source, means an amount of leakage of sealed radioactive sources been tested not higher than given in Table 1 GB 15849-1995
Limit.
3.6
A unique name (number, letter or combination of both) identifies the particular type of sealed radioactive sources.
3.7
Refers to a radioactive material within a sealed radioactive sources practically insoluble in water, it can not be diffused into the material.
3.8
Original sample for a radioactive source, which is manufactured with the same type all models sealed radioactive sources.
3.9
In order to provide adequate confidence indicates that an entity can meet the quality requirements, implemented within the quality system and demonstrated as needed full
Department planned and systematic activities.
3.10
Radionuclides into the human body, its release of radiation on the human body extent of the damage.
3.11
Sealed in a housing with a material or a combination of radioactive material. Under specified conditions of use and normal wear and tear, such a package
Shell or bonding material sufficient to maintain sealability source.
3.12
Some reproductions of sealed radioactive sources, the real structure and the sealing material, they represent the same as the source of its cladding, but the radioactive substances Mining
Substance instead of physical and chemical properties as close as possible, and contains only trace amounts of radioactive material.
Note. the tracer should be soluble in the solvent, the solvent can not be etched cladding, and is consistent with the tracer having maximum activity in the test environment (e.g., about
1MBq137Cs).
3.13
It contained within or close to the source in the source holder Torr sealed source.
3.14
Fixed or movable mechanical means for securing the carrier or the source.
3.15
Sealed sources stored in the shield apparatus is irradiated, thus providing a certain degree of mechanical protection use.
4 represents a method of grading and
4.1 Representation
Hierarchical representation of the source is sealed with GB 4075 /, after determining the classification indicates the year with a standard approved by four digits, then
It is separated by a slash symbol (/), plus a letter, then the five digits and comprises one or more digital parentheses.
Letters must be C or E.
--- C represents the activity sealed source does not exceed a predetermined level in Table 3.
--- E represents Table activity sealed source exceeds a third predetermined level.
Five level digital representation, according to the order of Table 2 are as follows. temperature characteristic, external pressure properties, impact properties, vibration characteristics and puncture properties.
If desired, the brackets can be added to a digital representation of a digital or more has passed the bending test source categories. Certain shape
Shaped source (elongated source, brachytherapy needle) bending test shown in Table 1, the specific requirements see 7.7. In order to meet the test criteria, you may want to be more than
Replications and inspection to describe. The bend test is not required, the brackets may be omitted.
Example.
--- a typical industrial photographic unprotected source can be expressed as. "GB 4075/2003/C43515 (1)" or "GB 4075/2003/C43515";
--- a typical brachytherapy source may be denoted as "GB 4075/2003/C53211 (8)";
--- a typical radiation source device may be represented as "GB 4075/2003/C53424 (4.7)".
4.2 rating
Hierarchical levels in Tables 1 and 2. Table 2 shows the various levels by increasing the stringency of environmental test conditions.
Table 1 bending test rating
Bending test Level 1 2 3 4 5 6 7 8 ×
Referring to the terms of the exemption
Bending test
7.7.1
Bending test
7.7.1
Bending test
7.7.1
Bending test
7.7.1
Bending test
7.7.1
Bending test
7.7.2
Bending test
7.7.3
special
test
Static pressure
S. F. =
100N
(10.2kg)
500N
(51kg)
1000N
(102kg)
2000N
(204kg)
4000N
(408kg)
Table 2 Performance Grade sealed source (represented by 5 digits)
test
content
level
1 2 3 4 5 6 ×
Temperature -40 ℃ exemption
(20min)
+ 80 ℃ (1h)
-40 ℃ (20min)
+ 180 ℃ (1h)
-40 ℃ (20min)
+400 ℃ (1h) and
To 400 deg.] C to 20 ℃
Thermal shock
-40 ℃ (20min)
+600 ℃ (1h) and
To 600 deg.] C to 20 ℃
Thermal shock
-40 ℃ (20min)
+800 ℃ (1h) and
To 800 deg.] C to 20 ℃
Thermal shock
special
test
External pressure exemption
The absolute pressure
25kPa to atmospheric pressure
The absolute pressure
25kPa to 2MPa
The absolute pressure
25kPa to 7MPa
The absolute pressure
25kPa to 70MPa
The absolute pressure
25kPa to 170MPa
special
test
Impact-free 50g
, Falling distance
1m or its equivalent in impact energy
200g, falling distance
1m or its equivalent in impact energy
2kg, falling distance
1m or its equivalent in impact energy
5kg, falling distance
1m or its equivalent in impact energy
20kg, falling distance
1m or its equivalent in impact energy
special
test
Vibration-free
In the 49ms-2 (5g) a
To under 25 Hz
500Hz test three times,
Every time 10min
In the 49ms-2 (5g) a
To under 25 Hz
50Hz between peak and peak
Amplitude 0.635mm
When, 50Hz to 90Hz
And 98 ms-2 in
Lower (10g) a condition
90Hz to 500 Hz
Above all test three times,
Every time 10min
Vibration between the peak and peak
Width is 1.5mm,
25Hz to 80Hz and
In 196ms-2 (20g) a
To under 80 Hz
Above 2000Hz are test
Test three times, each time 30min
Not required Not required
special
test
Puncture-free
Hammer weight 1g, falling from
Or the equivalent impact from 1m
Hammer weight 10g, falling
Or equivalent distance of 1m red
Can strike
Hammer weight 50g, falling
Or equivalent distance of 1m red
Can strike
Hammer weight 300g, drop
Or equivalent distance of 1m red
Can strike
Hammer weight 1kg, falling
Or equivalent distance of 1m red
Can strike
special
test
a maximum amplitude of acceleration.
Classification given in Table 4 fire, explosion and does not consider the effects of corrosion. In the evaluation of sealed sources, producers and users should be considered a fire,
The possibility of explosion and corrosion events and consequences of such an event may cause. When it is determined the need for special tests, the following should be considered
factor.
a) the consequences caused by the leakage of radioactive material;
b) an amount of a sealed source of radioactive material;
c) toxicity radionuclides;
d) Physical and chemical forms of the radioactive material;
e) a source storage, transfer and use environment;
f) Protection in a sealed source or combination of sources provided an apparatus.
If necessary, additional users and producers should agree sealed sources tested.
Annex D gives an example of a special test.
4.3 determine the level
Each seal type source level should be determined in one of the following methods.
--- Press each test shown in Table 2, use the same type (sample source, the source of false sealed source or analog) actual test two sources.
--- If you have previously carried out these tests and has proved sealed source qualified.
Each test different samples can be used.
Examines the source should be able to maintain its seal sealing performance to determine whether the standard. After each inspection, visual inspection application source End
The whole of damage, a leak test should be conducted according to appropriate GB 15849-1995. When doing analog source leak detection, the selected party
Sensitivity of the method should be suitable.
When the source has a multilayer envelope seal, the test seal having at least one layer of the cladding, it is determined to be inspected.
5 activity level requirements
Appendix A shows four sets toxic radionuclides, sealed sources predetermined activity values in Table 3, the activity is lower than the predetermined value, the specific
The use and design does not require a separate evaluation.
Table activity level specified by the packet toxic radionuclides 3
Radionuclide group
(See Appendix A)
Predetermined activity/T Bq (Ci)
A leachable non-leachable b
A 0.01 (approximately 0.3Ci) 0.1 (about 3Ci)
B1 1 (about 30Ci) 10 (about 300ci)
B2 10 (approximately 300Ci) 100 (about 3000Ci)
C 20 (approximately 500Ci) 200 (about 5000 Ci)
a leachable. According to GB 15849-1995 5.1.1, the source core 50 ℃ 100mL immersed in still water, 4h, water is greater than the radioactivity
0.01% total activity.
b non-leachable. 5.1.1 predetermined based 15849-1995 GB , the source core 50 ℃ 100mL immersed in still water, 4h, low water radioactivity
0.01% to the total activity.
When activity sealed source exceeds a predetermined value, to deal with the particular use and designed for further evaluation. To facilitate fractionation, the production should be based on
Table 3 activity level considering a sealed source.
Unless it is needed only when the sealed source activity exceeds a predetermined value as shown in Table 3 to be considered for fire, explosion, corrosion and toxic radionuclides
Effects were evaluated. If the activity exceeds a predetermined value, the classification should be considered sealed sources according to different situations. If the activity does not exceed
Value specified in Table 3, without further consideration of the toxicity of soluble and can be used directly in Table 4.
6 performance requirements
6.1 General requirements
All sealed sources should be tested after manufacturing, contamination test value of less than 200Bq, i.e. deemed source through contaminated test. The test
One of the tests specified in 5.3 shall GB 15849-1995.
All sealed sources should be tested after manufacture to ensure no leakage. The test shall be in a prescribed or GB 15849-1995
More than one method.
All sealed source should be measured after manufacture, to determine the radiation output.
Activity sealed source of radioactive material contained shall be estimated. This result can be measured by the amount of the radiation output by or used in the production of
The batch feed of estimated radioactivity measurements.
Samples were sealed source should be the standard of the test method in Chapter 7, graded according to the provisions of Chapter 4.
Level sealed radioactive sources typically used in Table 4 (performance) required
Use sealed source
Sealed source level (determined by test)
Temperature and pressure shock and vibration pricking
Industrial Radiography
Sealed source 43515
Source apparatus 43313
Medical
Radiographic 32312
γ radiation teletherapy 53524
Brachytherapy [6] a 5 3 2 1 1
The applicator surface b 4 3 3 1 2
γ meter (high energies)
Unprotected Source 43333
The source apparatus 43232
β instrument, low energy γ or x-ray fluorescence analysis instrument
b 3 3 2 2 2
Oil Field 56522
Hygrometer and portable densitometer (including hand-held or vehicle-mounted) 43333
Usually neutron source applications (not including reactor start) 43323
Instrument calibration source, activity > 1MBq 2 2 2 1 2
γ irradiation source [3], [5]
Class Ⅰ b 4 3 3 2 3
Ⅱ, Ⅲ and Ⅳ class c 5 3 4 2 4
Ionizer
Chromatography 32211
Static eliminator 22222
Smoke detector b 3 2 2 2 2
This type of a source may be severely deformed during use, producers and users should agree additional or specialized test procedures.
b does not include inflation source.
c may be a source device or source assembly for examination.
Each seal shall be identified by the source with Clause 8, including a certificate of the contents of inspection results and the like as required Chapter 9.
Source sealed enclosure should be compatible with the content on the physical and chemical properties. If the seal is directly illuminated by the source of production, the cladding should not contain
A significant amount of radioactive material unless such material can be firmly combined with the cladding material, and can show a sealing source is not leaking.
Tracer analog sources should be dissolved in a solvent, the solvent can not be etched cladding, and has an amount of tracer used in a test environment suitable for feeding
Line Leak maximum activity test (for example, about 1MBq137Cs).
6.2 Typical requirements
Sealed source, typically using some minimum performance and source element or the source apparatus in claim Table 4.
It may require one or more bending test, predetermined see 7.7.
15 (i.e., L/D≥15) activity test source region length (L) ratio of the minimum outer housing diameter (D) greater than or equal to the required bend specimen
Test See 7.7.1. For example, for sealing the irradiation source class Ⅰ apparatus, required to achieve level 4, Ⅱ, Ⅲ and Ⅳ irradiation apparatus is required to achieve the class
Level 5.
The active region length (L) ratio of the minimum outer housing diameter (D) equal to 10 or greater than 10 (i.e., L/D≥10) source and activity test head
Is equal to or larger than 100mm (i.e. L≥100mm) test source, bending test requirements is 7.7.2, and 7 to achieve.
The active region length (L) is greater than or equal to 30mm (i.e. L≥30mm) type of brachytherapy needle sealed sources, the required bending test, see
7.7.3, and required to achieve 8.
These requirements are considered normal and appropriate use of dangerous accidents, but does not include exposure to fire, explosion or corrosion in the case. Sealed source
Typically mounted in the apparatus, when the level value is determined for a particular purpose, taking into account an additional sealing protection provided by the source means. because
Here, the use of all listed in Table 4, the level value corresponding to the predetermined test, are required to be sealed source. Type ionizer except that
Available entire source or source assembly inspection apparatus.
These predetermined inspection uncovered usage of all sealed sources, specific conditions of use or the case where table associated with the regulation of potential accidents 4
Given classification is not entirely consistent, producers and users should be under different circumstances, consider appropriate tests.
Table 4 shows the numbers refer to the numbers in Table 2 level.
Note. IAEA inspection related to special form radioactive material [1], and should not be widely used, but as an additional test is appropriate.
6.3 determine the level of procedures and performance requirements
6.3.1 Toxicity group consisting of a radionuclide is determined Appendix A.
6.3.2 activity values in Table 3 in accordance with a predetermined determination.
6.3.3 If the activity sealed source does not exceed a predetermined activity values in Table 3, to deal with fires, explosions, the risk assessment for corrosion, if confirmed
No significant risk, may be sealed source and the minimum level required to use (see 6.2). If confirmed to have a significant hazard shall try to request
Conduct a comprehensive assessment test (see 4.2), paying particular attention to temperature and shock caused dangerous.
6.3.4 If the sealing sheet 3 to allow the source activity exceeds the level, the deal requires the test to be evaluated, respectively, comprising a source design, with specific
Because of the way and the danger of fire, explosion, caused by corrosion.
6.3.5 determining a lowest level in a particular use or purpose of the sealed source requirements, performance requirements can be obtained directly from Table 1 and Table 2
standard.
6.3.6 source level may be sealed in Table 1, Table 2 is determined, in accordance with Table 4 to select the appropriate application.
Since according to Table 2 are strictly in order of increasing, from level 1 to 6 are arranged, thus sealing the determined level may be applied to any source
It has the same or lower than the stringent performance requirements of specific applications.
7 test methods
7.1 Overview
Test method given in this chapter is to determine an acceptable level of performance. All indicators specified minimum requirements. Other methods, if
Prove this chapter may also be at least equivalent to the method. In addition to the temperature test, all tests should be carried out at ambient temperature.
Level after testing to determine the source shall be 4.3.
7.2 temperature test
7.2.1 device
Volume heating or cooling means in the inspection zone is at least 5 times the sample volume. If the heating with a gas or fuel oil, the inspection.
Process, should always maintain an oxidizing atmosphere.
7.2.2 Method
All tests shall be carried out in the atmosphere.
NOTE. In the low temperature test, allowing the use of a lower temperature than required to obtain carbon dioxide (dry ice atmosphere).
Source below ambient temperature sealing test, test temperature should be reduced from the ambient temperature within 45min. Above ambient temperature for the subject
Seal test source should be within a time less than specified in Table 5, the test temperature was raised from ambient temperature.
Table 5 above ambient temperature test temperature - time relationship
Test temperature/℃ maximum time limit/min
800a 70
a6 level test and temperature test method is similar to a predetermined IAEA [1].
For Level 2 and Level 3 testing, sealing at least 1h source remains above the test temperature, and then slowly cooled in a furnace or laboratory atmosphere
To ambient temperature.
For four, five, six test, sealing at least 1h source remains above the test temperature, in the 15s loop of the sample into thermal shock
Ambient temperature water (about 20 ℃), the flow rate per minute of water should be at least 10 times the volume of the source, such as still water, the source should be at least the volume of water
20 times.
7.3 external pressure test
7.3.1 Equipment
Pressure gauge should have just calibrated, and the pressure range of at least 10% greater than the test pressure. Absolute gauge read at least 20kPa
Air pressure. Low and high pressure testing can be performed in a different chamber.
7.3.2 Method
The source is placed in a small sealed chamber and exposed to the test pressure, this operation is performed twice, each time 5min. Two test operation
Between pressure should be restored to atmospheric pressure.
Low pressure tests carried out in air, high pressure hydraulic test method, the source and the sealing m...
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