|
US$419.00 · In stock
Delivery: <= 3 days. True-PDF full-copy in English will be manually translated and delivered via email.
GB 10252-2009: Regulations for radiation protection and safety of gamma irradiation facilities
Status: Valid GB 10252: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB 10252-2009 | English | 419 |
Add to Cart
|
3 days [Need to translate]
|
Regulations for radiation protection and safety of gamma irradiation facilities
| Valid |
GB 10252-2009
|
| GB 10252-1996 | English | 399 |
Add to Cart
|
3 days [Need to translate]
|
Standards for radiation protection and safety of 60Co irradiation facility
| Obsolete |
GB 10252-1996
|
| GB 10252-1988 | English | RFQ |
ASK
|
3 days [Need to translate]
|
Regulations for radiation protection of 60Co irradiation processing facility
| Obsolete |
GB 10252-1988
|
PDF similar to GB 10252-2009
Standard similar to GB 10252-2009 GB 13172 GB/T 15849 GB/T 12714 GB 12951 Basic data | Standard ID | GB 10252-2009 (GB10252-2009) | | Description (Translated English) | Regulations for radiation protection and safety of gamma irradiation facilities | | Sector / Industry | National Standard | | Classification of Chinese Standard | F51 | | Classification of International Standard | 13.280 | | Word Count Estimation | 18,148 | | Date of Issue | 2009-06-19 | | Date of Implementation | 2010-06-01 | | Older Standard (superseded by this standard) | GB 10252-1996 | | Quoted Standard | GB 3095; GB 17568; GB 18871-2002; HJ/T 2.2-1993 | | Regulation (derived from) | Announcement of Newly Approved National Standards No. 9, 2009 (No. 149 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 specifies the use of Class I radioactive sources �� irradiation radiation and pollution control division of the radiation in the workplace, radiation protection and safety design, environmental assessment irradiation, radiation safety management, radiation safety testing, irradiation equipment decommissioning and emergency requirements. This standard applies to Class I radioactive sources using �� irradiation facility siting, design, construction, operation and decommissioning of radiation protection and safety. | GB 10252-2009: Regulations for radiation protection and safety of gamma irradiation facilities---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.
Regulations for radiation protection and safety of gamma irradiation facilities
ICS 13.280
F51
National Standards of People's Republic of China
Replacing GB 10252-1996
Radiation protection and safety norms γ Irradiation Facilities
Posted 2009-06-19
2010-06-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Table of Contents
Preface Ⅰ
1 Scope 1
2 Normative references 1
3 Terms and definitions
4 radiation and pollution control 2
5 2 division of radiation in the workplace
6 Radiation Protection and Safety Design 2
Environmental Assessment irradiation apparatus 3 7
8 Radiation Safety Management 3
9 Radiation Safety Inspection 4
Managed 10 radioactive sources 5
11 irradiator retired 5
12 6 Emergency
Appendix A (informative) irradiation chamber shielding and protection design calculation 7
Appendix B (normative) concentration limits of harmful gases and monitoring 12
Produce Annex C (informative) harmful gases and diffusion calculation 13
Foreword
All the technical contents of this standard is mandatory.
This standard replaces GB 10252-1996 "radiation protection and safety standards cobalt-60 irradiation facilities."
This standard compared with GB 10252-1996, the main changes are as follows.
--- By the name of the standard "cobalt-60 radiation protection and safety standards irradiation apparatus" with "radiation protection and safety γ Irradiation Facilities
specification";
--- "Scope" to add a chapter include some content, expanding the scope of application;
--- "Normative references" All has been modified;
--- Added "Terms and Definitions" chapter;
--- "Radiation and Pollution Control" made some changes;
--- Remove the original "division and workplace requirements" chapter, "non-restricted zone" a;
--- Increased "radiation protection and safety," a chapter;
--- Increased "environmental assessment irradiation apparatus" chapter;
--- Original "radiation protection and safety management" with "Radiation Safety Management";
--- Remove the original "technical requirements for radiation protection and safety" and "security analysis irradiation apparatus" two chapters;
--- Original "inventory and inventory of radiation sources" to "Management of Radioactive Sources";
--- The original "Radiation protection and safety testing content" and "radiation monitoring" Merge to "detect radiation safety";
--- Added "retired irradiation apparatus" chapter;
--- Original "accident and emergency radiation protection" to "emergency";
--- Added Appendix A and Appendix C, recommended mathematical models for calculating radiation protection and harmful gases.
This standard is GB 17568 "γ irradiation device is designed and constructed using standard" support standards.
Appendix B of this standard is a normative appendix, Appendix A, Appendix C are informative appendices.
The standard proposed by China National Nuclear Corporation.
This standard by the National Standardization Technical Committee of nuclear energy.
This standard was drafted. Beijing three strong nuclear radiation Engineering Technology Co., MEP Nuclear and Radiation Safety Center, Beijing radio
Line Applied Research Center.
The main drafters of this standard. Wang Chuan Zhen, Zhou Qifu, Liuyi Gang, Liuqiu Rong Fan deep roots, Jang Hyuk coral, Chen Jian, Peng Wei, Fu Jie.
This standard was first released in December 1988, in December 1996 the first amendment, this is the second revision.
Radiation protection and safety norms γ Irradiation Facilities
1 Scope
This standard specifies the use of γ irradiation apparatus Ⅰ class sources of radiation and pollution control division, radiation protection and radiation in the workplace
Environmental evaluation of safety design, the irradiation apparatus and the radiation safety management, radiation safety testing, irradiation facilities decommissioning and emergency requirements.
This standard applies to the use of the site class Ⅰ γ irradiation apparatus radioactive sources, design, construction, operation and decommissioning of radiation protection and safety.
2 Normative references
The following documents contain provisions which, through reference in this standard and become the standard terms. For dated references, subsequent
Amendments (not including errata content) or revisions do not apply to this standard, however, encourage the parties to the agreement are based on research
Whether the latest versions of these documents. For undated reference documents, the latest versions apply to this standard.
GB 3095 Ambient Air Quality Standard
GB 17568 γ irradiation facilities design and construction specifications and use
GB 18871-2002 ionizing radiation protection and safety of radiation sources basic standards (IAEA Safety Series, NEQ)
HJ/T 2.2-1993 Environmental Impact Assessment Technology Guidelines
3 Terms and Definitions
GB 17568 and established in the following terms and definitions apply to this standard.
3.1
Within the irradiation facility enclosed by a radiation-shielding material with, radiation processing and in working condition due to safety measures for personnel can not enter the interlock
Space.
3.2
Penetrating power strong radiation in matter, generally refers to γ radiation, X-radiation and neutron radiation. This standard refers specifically to shield the irradiation chamber wall table
Surface water surface, the roof and a reservoir wells transmission out of γ radiation.
3.3
Important safety control system irradiation apparatus, wherein the operation of such components are interrelated, each action parts are subject to pre-regulation
Given state and (or) controlled conditions, so long as either a component of any state and (or) does not meet the pre-conditions for the provisions of irradiation can be prevented
Sources from the storage device state put into use, or to have been put into use radioactive sources or are immediately returned to the storage state, or resistance
Personnel from entering the irradiation device is irradiated from the irradiation chamber to make it.
3.4
The source or the use of a particular practice is possible to predict and estimate the impact on the environment carried out, including the size of the source or practice with special
Of the overview of the status of the site or workplace environment analysis and environmental impact under normal, abnormal and may cause accidents or consequences
Analysis.
3.5
Environmental protection department under the State Council issued on the basis of the safety review, together with its holder to comply with the specific requirements and conditions
Radiation safety license.
3.6
Reached the end of life of the radionuclide or find a leak or licensees are no longer expected to use radioactive sources specified by the manufacturer.
4 radiation and pollution control
4.1 Individual Dose Control
4.1.1 radiation workers occupational and public exposure dose limits should be in accordance with the requirements of GB 18871-2002.
4.1.2 irradiator engineering design, operation and decommissioning, radiation protection dose constraint value is defined as.
a) Radiation Workers' Individual annual effective dose values 5mSv;
b) members of the public individual annual effective dose values 0.1mSv.
4.2 Radioactive pollution control
4.2.1 radioactivity concentrations in well water reservoir 60Co source should be controlled 10Bq/L or less.
4.2.2 source storage wells emissions shall meet the following requirements.
a) Monthly discharged into the sewer 60Co total activity should not exceed 1 × 106Bq;
b) 60Co total activity every emissions should not exceed 1 × 105Bq, and after each discharge with no less than three times the amount of water discharged
rinse;
c) discharge only after the approval of the regulatory authorities.
4.2.3 in accordance with GB 18871-2002 Table B. 11, staff clothing, surface and workplace equipment, tools, floors and other surfaces β
Control the level of radioactive contaminants in Table 1.
Table 1 Surface β radioactive pollution level Substances Control unit becquerels per square centimeter
Surface type β radioactivity
Tables, equipment, walls, floors,
Control area 4 × 10
Supervised area 4
Overalls, gloves, work shoes
Control area
Supervised area
Hands, skin, underwear, socks, work 4 × 10-1
When Equipment & Supplies 4.2.4 in the workplace, after decontamination, pollution levels below 0.8Bq/cm2, with a measurement mechanism by qualified and
After regulatory permission to make use of ordinary objects, but does not apply to cookware.
Divided by 5 radiation in the workplace
6.4 in accordance with the provisions of GB 18871-2002, radiation irradiation device into place.
a) control area. irradiation chamber and fan Road;
b) supervised area. cargo handling area between the irradiation chamber roof control room, ventilation, equipment room, treatment rooms and other areas.
6 Radiation Protection and Safety Design
6.1 shield
6.1.1 shield should be designed to ensure the irradiation chamber radiation shielding integrity and security. For weak radiation shielding parts (such as ventilation and wear
Wall tunnels, etc.), compensatory measures should prevent leakage beam; irradiation chamber should be designed taking into account the thickness of the roof penetrating radiation and sky diffuse; fan channel design
Fans should be crossing the external radiation dose of radiation workers to meet the requirements of 4.1.2; at the maximum design loading source volume, the outer surface of the shield dose levels
It shall also meet the requirements of 4.1.2.
6.1.2 source storage wells (including auxiliary shaft) should be designed to ensure that a reservoir wells radiation shielding integrity and security. Wells and well equipment cladding
It should be used in good corrosion resistance of stainless steel and ensure good sealing performance and a certain load-bearing capacity; the bottom of the pond should have penetrations (such as
Pipes, plugs). Any penetrations through the wall of the pool should be below the normal water level of not less than 30cm.
At the maximum design loaded source activity, well above the dose levels should meet the requirements of 4.1.2.
6.1.3 shielding design and computing model calculation parameters refer to Appendix A.
6.2 Irradiation Facility Security System
6.2.1 irradiator design safety systems should follow the principle of defense in depth, and to meet the requirements of GB 17568.
6.2.2 Security facilities should ensure that.
--- All safety facilities is active, normal state;
--- Or source before mistakenly left unattended in the irradiation chamber, able to help themselves stay as erroneous;
--- Security sources when not in place, people can not enter the irradiation chamber;
--- A reservoir wells water level indication and alarm when the water level dropped to a critical level security and timely replenishment;
--- Safe and effective water treatment system, water quality meet the requirements;
--- Staff can not fall into the well;
--- Having sufficient mechanical protection of radioactive sources, to avoid collision.
6.3 of harmful gases
6.3.1 radiation concentration generated by the decomposition of ozone and other harmful gases does not exceed the allowable value, the control and monitoring requirements concentration Mitsuke
Record B.
6.3.2 ozone generation and emission calculation model and its parameters, see Appendix C.
Environmental Assessment 7 irradiation apparatus
7.1 owners prior to construction γ irradiation apparatus shall prepare an environmental impact assessment documents include radiation safety content analysis, and in accordance with national
Prescribed procedures for approval.
7.2 Radiation safety analysis should include analysis of normal conditions and accident conditions.
8 Radiation Safety Management
8.1 Regulated irradiator
Location 8.1.1 irradiator, design, construction, operation and decommissioning shall be in accordance with relevant regulations, to regulatory authorities apply approved
Or after approval before implementation.
8.1.2 source irradiator design maximum loading capacity increases or facilities involved in radiation safety devices have changed owners regulatory authorities should lodge a
Please, after their radiation protection and safety certification before implementation.
8.2 Radiation safety responsibilities of owners
The owners of the radiation safety of the irradiation apparatus fully responsible for radiation protection and safety should be developed outline, specify the person in charge of radiation protection, with
Equipment or hiring qualified experts.
8.3 Radiation Protection Leader
Owners should be set radiation protection and safety agencies, and specify the person responsible for radiation protection, and give it the appropriate rights, if needed for the operation and spoke
When there is a potential conflict between the Radiation Safety, a priority of radiation safety.
The person in charge of radiation protection responsibilities include.
--- Provide operating instructions to all operators, maintenance personnel and other related personnel, training assessment and confirm that they have
Master, follow these instructions;
--- Inlet passage control zone management;
--- Ensure radiation worker radiation doses to meet the requirements of 4.1.2;
--- Verification arrangements radiation monitoring instruments;
--- Check the service records of radioactive sources and recording equipment;
--- Development of radiation safety testing program and organize the implementation;
--- Monitor individual dosimeters distribution and recovery, evaluate dose monitoring results;
--- Organize and conduct regular safety inspection procedures;
--- Appears radiation safety problems and timely reporting;
--- Development of contingency plans, arrange periodic drills to ensure their suitability and effectiveness;
--- Prepare an annual assessment report irradiator safety and protection conditions.
8.4 qualified experts
8.4.1 owners employ more than 5 years of radiation safety management experience and professional background and the title of senior staff as qualified experts.
Qualified experts to make recommendations on radiation safety within the regulatory issues related to the scope, should not bear the responsibility of the owners.
8.4.2 Qualified experts should provide advice and assistance when the owner needs.
--- Optimization of radiation protection;
--- Dosimetry and radiation monitoring;
--- Survey irradiation overdose events;
---staff training;
--- Radiation safety assessment and contingency plans;
--- New construction, renovation, expansion plans irradiator;
---Quality Control;
--- Emergency treatment.
8.5 Safety Culture
Owners should cultivate and maintain good safety culture to ensure that.
--- Development of radiation protection and safety in the first place policies and procedures;
--- To discover and address the impact of radiation protection and safety issues, the approach to be consistent with the importance of the issue;
--- Specifically related personnel (including senior executives) of the radiation protection and safety responsibility, radiation workers should be trained and have the
There are suitably qualified;
--- Clear relationship between radiation protection and safety and responsibility in decision-making;
--- Organization and establish effective channels of communication to keep radiation protection and safety information in all levels and sectors between owners
Smooth.
9 Radiation Safety Testing
9.1 routine daily inspection should include at least the following.
a) Working status indicator;
b) Radiation safety interlock control room display condition;
c) Lift the source and delivery system conditions;
d) personal alarm dosimeters and portable Dose Monitor;
e) a reservoir well water level;
f) ventilation systems.
9.2 regular monthly examination should include at least the following.
a) irradiating an indoor stationary radiation monitors.
b) a source of emergency lowering system.
c) source and a guide wire rope hoist, conveyor systems. If the tether appear overused phenomenon, should be replaced.
d) fill the water replenishment should check whether it is normal. As an exception, you should check wells for leaks and check the water supply system operation
situation.
9.3 General six months examination should include at least the following.
a) with annual maintenance of detection;
b) water quality and pollution detection;
c) environmental radiation levels;
d) all the equipment and automatic control system.
Detecting radiation source means to change or add source 9.4 shall include at least the following.
a) a reservoir of water and well water well radioactivity levels;
b) the number of radioactive sources;
c) loading a source container surface dose rate and Pollution;
d) Source tool handling and lifting equipment condition;
e) Individual Dose operator.
9.5 Radiation detection equipment installed after the source should include at least the following.
a) a source 24h after the radioactivity level of well water;
b) a source at the working position, the dose to the surrounding environment and workplace monitoring;
c) source in storage position on the side of a reservoir Inoue and radiation dose monitor chamber.
9.6 The operating organization should do more safety testing, the use of standardized forms records and annual assessment. Records should be kept to the irradiator
Retired.
Managed 10 radioactive sources
10.1 radioactive sources into the unit should hold a license, fill radioisotope import or transfer approval form, after the approval of the regulatory authorities
Before transfer.
Around 10.2 installation source and should make a detailed inventory of the accounting registration (including the type of radioactive sources, the number of coding each one source, and daily activity
Period, the location of the source frames, etc.), installed source personnel, radiation protection and the executives responsible for the signing, record-keeping to decommissioning.
10.3 should be checked annually shelves radioactive source without loss, make a record.
10.4 Source retired after delivery or return to the reservoir manufacturer shall filing procedures and records (including radioactive source coding, activity and date, go
Storage and delivery to date). The records shall be kept to the irradiator retired.
10.5 sources has reached its useful life specified by the manufacturer of the safe use of the period should be allowed to retire and promptly sent to storage.
10.6 Irradiation means the owners of the safety and security of radioactive sources responsible for its duties should include.
a) special attention to security decommissioning radioactive sources;
b) lost, stolen or missing radioactive sources should report the relevant departments in accordance with regulatory requirements.
Retired 11 irradiator
11.1 life
Irradiators life of 40a.
11.2 Extended Run
If you reach but the owners request an extension of life, it shall submit the regulatory safety evaluation report and other supporting information used by extension, the
After review approval, it may postpone the operation.
11.3 mandatory retirement
For various reasons, can not repair the damaged device should be forced its retirement.
11.4 decommissioning implementation
Irradiator sources within the device should be removed before retirement. After the removal of radioactive sources, should by the intelligence unit of the preparation of environmental impact assessment paper
Member, after approval by the regulatory authorities decommissioning.
12 emergency
12.1 Irradiation Facility owners should develop emergency plans, including the maximum credible accident analysis, emergency procedures and the like.
12.2 irradiator event of an accident, should take appropriate action in response to different situations immediately in accordance with the requirements of the emergency plan. Things happen
After it according to the requirements of the relevant provisions of timely reporting.
12.3 personnel involved in emergency treatment, should bring personal dose Alarm, and adapt to wearing personal dosimeters. To operate the whole process
Radiation protection personnel to monitor and record.
12.4 When emergency treatment to control radioactive contamination. Exceeding water pollution discharge standards to achieve purification to 4.2.2
Before discharge requirements.
12.5 The Client shall ensure that all necessary emergency supplies can be used normally in case of emergency, including.
--- Appropriate and functioning survey meter, measure the dose rate and radioactive contamination;
--- Direct reading personal dose Alarm;
--- Personal dosimeter;
--- Shielding materials and warning signs;
---communication device;
--- Survey meter battery backup, lighting appliances;
--- Stationery paper, including accident log;
--- Manual;
--- A copy of the emergency procedures.
Emergency supplies should be placed label clearly, easily taken out of the cupboard. Emergency supplies should be accompanied by a list of the cabinet. Or should be checked regularly to make
Immediately after use verification to ensure that all instruments exist and function properly, or replace as necessary.
12.6 Exposed personnel treatment and medical treatment, etc., should be dealt with in accordance with relevant regulations.
12.7 Accident pollutants generated in the process according to relevant regulations.
12.8 Accidents and the process to be documented and long-term preservation.
12.9 contingency plans should be regularly reviewed, at intervals of not more than 12 months. Such as operating status changes, or similar irradiator accident
After, contingency plans should be reviewed according to the situation. Review should ensure that.
--- Personnel list, and contact information is up to date;
--- Emergency equipment performance intact, complete supplies;
--- Predictable event processing program is timely.
12.10 All participants contingency plans should be trained to ensure its effective implementation tasks. The training should include familiarization, emergency pre-understanding
Case, learning to use the emergency materials, including Recalling previous accident lessons. Refresher training should be carried out to select the appropriate interval and recorded.
12.11 arrange for staff at appropriate intervals emergency training exercises. Applicability and effective contingency plans through exercises Assessment
Sex. If necessary, to modify the exercise program and contingency plans.
Appendix A
(Informative)
Irradiation chamber shielding and protection design calculation
A. 1 irradiation chamber shielding wall thickness determination
For γ irradiation means radioactive source is a board made up of many sources of rod-shaped, usually for 1.85 × 1016Bq (50 Wan Habitat
In) below the rank of sources, since the source frame size is small relative to the size of the irradiation chamber, when γ radiation shielding calculation approximate the following points
Source computing model does not produce large errors; but when reached one million sources Curie level and above, due to the larger size frame source, point source near this
Like computing model it is not reasonable. Therefore, the use of foreign mature point kernel integral Shielding Calculation programs such as QAD-CG calculation.
In the absence of the medium between the point source and probe points situation, γ-ray energy flux density probe points is calculated as shown in Equation (A.1).
Φ = S04πR2
(A.1)
Where.
Φ --- γ-ray energy flux density, in units of MeV seconds per square centimeter [MeV/(cm2 · s)];
S0 --- point source energy intensity per unit of MeV (MeV/s);
R --- from the point source and detection points between centimeters (cm).
Converted by number ICRP74 Publications (1996) Richard γ photon energy corresponding to the energy flux density 1.25MeV when the dose rate due to
Sub Hp = 1.765 × 10-5 (mSv/h)/[MeV/(cm2 · s)], obtained by the conversion rate of the probe point no dose shield when D.
Multiple needs effectively weaken the concrete shielding wall calculation see equation (A.2).
K =
D
Dm
(A.2)
Where.
Effectively weaken multiples k --- shield body;
Dose rates D --- no shield case of probe points, units per hour microsieverts (μSv/h);
Dm --- shielded Area vitro detection point dose constraint value corresponding to the dose rate in units of micro Greek per hour (μSv/h).
The k value, you can find the required concrete shielding wall thickness value. For a reservoir wells, water shield can be used to determin...
Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB 10252-2009_English be delivered?Answer: Upon your order, we will start to translate GB 10252-2009_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 10252-2009_English with my colleagues?Answer: Yes. The purchased PDF of GB 10252-2009_English will be deemed to be sold to your employer/organization who actually pays for it, including your colleagues and your employer's intranet. Question 3: Does the price include tax/VAT?Answer: Yes. Our tax invoice, downloaded/delivered in 9 seconds, includes all tax/VAT and complies with 100+ countries' tax regulations (tax exempted in 100+ countries) -- See Avoidance of Double Taxation Agreements (DTAs): List of DTAs signed between Singapore and 100+ countriesQuestion 4: Do you accept my currency other than USD?Answer: Yes. If you need your currency to be printed on the invoice, please write an email to [email protected]. In 2 working-hours, we will create a special link for you to pay in any currencies. Otherwise, follow the normal steps: Add to Cart -- Checkout -- Select your currency to pay. Question 5: Should I purchase the latest version GB 10252-2009?Answer: Yes. Unless special scenarios such as technical constraints or academic study, you should always prioritize to purchase the latest version GB 10252-2009 even if the enforcement date is in future. Complying with the latest version means that, by default, it also complies with all the earlier versions, technically.
|