|
US$299.00 · In stock
Delivery: <= 3 days. True-PDF full-copy in English will be manually translated and delivered via email.
GB 9132-2018: Safety requirements for near surface disposal of low and medium level radioactive solid waste
Status: Valid GB 9132: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB 9132-2018 | English | 299 |
Add to Cart
|
3 days [Need to translate]
|
Safety requirements for near surface disposal of low and medium level radioactive solid waste
| Valid |
GB 9132-2018
|
| GB 9132-1988 | English | 359 |
Add to Cart
|
3 days [Need to translate]
|
Regulations for shallow ground disposal of solid low-and intermediate-level radioactive wastes
| Obsolete |
GB 9132-1988
|
PDF similar to GB 9132-2018
Basic data | Standard ID | GB 9132-2018 (GB9132-2018) | | Description (Translated English) | Safety requirements for near surface disposal of low and medium level radioactive solid waste | | Sector / Industry | National Standard | | Classification of Chinese Standard | Z05 | | Classification of International Standard | 13.030 | | Word Count Estimation | 15,199 | | Date of Issue | 2018-07-10 | | Date of Implementation | 2019-01-01 | | Older Standard (superseded by this standard) | GB 16933-1997; GB 9132-1988 | | Quoted Standard | GB 12711; GB 14569.1; GB 18871; GB 50011; GB 50223; EJ 1186 | | Regulation (derived from) | Ministry of Ecology and Environment Announcement No.20 of 2018 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | | Summary | This standard specifies the general requirements for near-surface disposal of radioactive solid waste, and general requirements for site selection, design, construction, operation, shutdown, monitoring, and environmental monitoring, safety process analysis and quality assurance of near-surface disposal sites. . This standard applies to near-surface disposal of low- and medium-level radioactive solid waste. Medium-level radioactive solid waste, because it contains a considerable amount of long-lived nuclides, cannot rely solely on monitoring measures to ensure the safe disposal of waste, and requires a higher degree of containment and segregation than low-level radioactive solid waste. This standard does not apply to the disposal of radioactive waste, natural radioactive waste generated during the development and utilization of uranium (��) ore, and the cave disposal and drilling disposal of radioactive waste. | GB 9132-2018: Safety requirements for near surface disposal of low and medium level radioactive solid waste
---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.
(Safety regulations for near-surface disposal of low- and medium-level radioactive solid wastes)
ICS 13.030
Z 05
National Standards of People's Republic of China
Replace GB 9132-1988 GB 16933-1997
Near-surface disposal of low- and medium-level radioactive solid waste
Safety regulations
Safety requirements for near surface disposal of low and medium level
Radioactive solid waste
Published on.2018-07-10
2019-01-01 implementation
State market supervision and administration
Ministry of Ecology and Environment released
Content
Foreword...ii
1 Scope...1
2 Normative references...1
3 Terms and Definitions...1
4 General... 2
5 waste package...2
6 Site selection...3
7 Design and construction of the disposal site...5
8 Disposal of the disposal site...6
9 Disposal of the disposal site...7
10 Monitoring after the disposal site is closed...8
11 Environmental monitoring of the disposal site...8
12 Safety full process system analysis...8
13 Quality Assurance...9
Appendix A (Normative Appendix) Requirements for Waste Package Archives...11
Foreword
To implement the Law of the People's Republic of China on Environmental Protection, the Law of the People's Republic of China on Prevention and Control of Radioactive Pollution
The Nuclear Safety Law, to prevent and control radioactive waste pollution, improve environmental quality, and develop this standard.
This standard specifies the general requirements for the near surface disposal of radioactive solid waste, and the site selection, design, construction and transportation of the near surface disposal site.
General requirements for line, shutdown, monitoring, and environmental monitoring, safety process analysis, and quality assurance.
This standard is a revision of the Regulations on Shallow Stratigraphic Disposal of Low and Medium Level Radioactive Solid Wastes (GB 9132-1988).
This standard was first published in 1988. This is the first revision.
The main contents of this revision.
-- The standard name was changed to "Safety Regulations for Near-surface Disposal of Low- and Medium-Level Radioactive Solid Wastes";
-- Added "2 normative references";
-- Add "waste pack", "safety full process system analysis", "passive safety characteristics", etc. in "3 terms and definitions"
language;
-- Revised the “Basic Requirements for Waste Disposal” in the “4 General Rules”. Change "site selection" to Chapter 6, "Waste Pack"
As Chapter 5;
-- According to the provisions of HJ/T 23, the “site selection procedure” in “6 Site Selection” was revised to increase environmental protection requirements;
-- The activity concentration of low-level radioactive solid waste proposed for near-surface disposal should meet the requirements of the Classification of Radioactive Waste. supplied
The requirements for waste characteristics, and the “waste packaging requirements” were revised according to the relevant standards of our country, and the “waste packaging requirements” were changed to “waste”.
"Package requirements", stipulate that the disposal site should establish waste acceptance criteria;
-- Defining the requirements for the disposal unit in the “Design and Construction of the Disposal Site” for receiving high surface dose rate waste packages
At the disposal site, the requirements for “equipment that should be set up for remote or remote transport and placement of waste packages” are proposed;
-- Added the chapter on establishing a digital information management system for waste disposal and formulating a contingency plan in the chapter "Operation of 8 Disposal Sites"
In the stage of simultaneous construction and operation of the disposal site, it is proposed to ensure that relevant construction activities do not affect the safety of operating facilities.
begging;
- In the chapter "Close of 9 Disposal Sites", the relevant contents of the three phases after the closure of the disposal site were deleted, and the disposal was specified.
The closure of the site shall comply with the requirements for closing the license file;
- Increase "10 monitoring after shutdown of the disposal site" and "Environmental monitoring of the disposal site";
-- Change "9 Safety Evaluation" to "12 Safety Full Process System Analysis";
-- Add "13 Quality Assurance";
-- Increase the requirements for the contents of the waste package file in Appendix A (Normative Appendix).
From the date of implementation of this standard, the Provisions for the Disposal of Low-Level and Medium-Level Radioactive Solid Wastes (GB 9132-1988),
Waste Acceptance Guidelines for Near-surface Disposal of Radioactive Waste (GB 16933-1997) is abolished.
Appendix A of this standard is a normative appendix.
This standard is formulated by the Department of Radiation Source Safety Supervision and the Department of Science and Technology Standards of the Ministry of Ecology and Environment.
This standard was drafted. China Nuclear Power Engineering Co., Ltd.
This standard is approved by the Ministry of Ecology and Environment on July 10,.2018.
This standard has been implemented since January 01,.2019.
This standard is explained by the Ministry of Ecology and Environment.
Safety regulations for near-surface disposal of low- and medium-level radioactive solid wastes
1 Scope of application
This standard specifies the general requirements for the near surface disposal of radioactive solid waste, and the site selection, design, construction and transportation of the near surface disposal site.
General requirements for line, shutdown, monitoring, and environmental monitoring, safety process analysis, and quality assurance.
This standard applies to near-surface disposal of low- and medium-level radioactive solid waste. Medium level radioactive solid waste due to considerable amount
Long-lived nuclides cannot rely solely on guardianship measures to ensure the safe disposal of waste and require a higher level of exposure than low-level radioactive solid waste
Inclusion and isolation measures.
This standard does not apply to the disposal of radioactive waste, natural radioactive waste generated during the development and utilization of uranium ore, and radiation.
Cave disposal and drilling disposal of waste.
2 Normative references
This standard refers to the terms of the following documents. For undated references, the valid version applies to this standard.
GB 12711 Low and medium level radioactive solid waste packaging safety standards
GB 14569.1 Low and medium level radioactive waste solidified body performance requirements - cement solidified body
GB 18871 Basic standards for ionizing radiation protection and radiation source safety
GB 50011 seismic design code for buildings
GB 50223 Seismic fortification classification standard for building engineering
EJ 1186 Characterization of radioactive waste bodies and waste packages
Classification of Radioactive Waste (Ministry of Environmental Protection, Ministry of Industry and Information Technology, National Defense Science and Technology Industry Bureau Announcement No. 65 of.2017)
3 Terms and definitions
The following terms and definitions apply to this standard.
3.1
Near surface disposal
The radioactive waste is placed in a facility tens of meters below the surface of the ground or below the surface of the earth, and an engineering barrier is placed.
3.2
Waste package
Waste-prepared products, including waste bodies and containers, as well as possible linings for handling, transport, storage and/or
Disposition requirements.
3.3
Organized control
Control of waste disposal sites by government agencies or their designated units. This control includes active (monitoring, supervision and facilities)
Maintenance) or passive (restricted land use) controls.
3.4
Close closure
Shutdown includes normal shutdown and abnormal shutdown. Closing operations generally include backfilling, covering disposal facilities, terminating and ending related auxiliary facilities
The activities carried out have permanently closed the disposal site.
3.5
Safety full process system analysis safety case
Refers to the documentary integration of arguments and arguments in support of and support for the scientific, technical, administrative and managerial aspects of the safety of the disposal site, covering the appropriate site
Suitability, safety of the design, construction and operation of the facility, rationality of the radiation risk assessment, and all work related to the safety of the disposal site
Adequacy and reliability.
3.6
Passive safety features
Refers to the intrinsic safety features of the disposal site to contain radioactivity, to isolate radioactive waste and to limit the release of radionuclides to the biosphere, including entities
Barriers (such as engineering barriers, natural barriers and shielding), material properties (such as the adsorption properties of natural or artificial materials on radionuclides, etc.)
And the favorable characteristics of the site (such as terrain and geological conditions that are conducive to the stability of the disposal site).
4 General
4.1 Basic safety requirements for waste disposal
4.1.1 Waste disposal should follow the principle of defense in depth and set up multiple barriers (including waste bodies, packaging containers, disposal units, geological bodies).
Etc., establish and maintain an effective defense against radiological hazards and protect humans and the environment from the harmful effects of ionizing radiation.
4.1.2 During the site selection, design, construction, operation and shutdown of the disposal site, effective measures should be taken to ensure the stability of the disposal site.
4.1.3 The disposal site should contain radioactivity, sequester radioactive waste, and limit the release of radionuclides to the biosphere (for low level radioactive solids)
The inclusion and isolation time of body waste is generally 300 to 500 years).
4.1.4 The disposal system should be secured by multiple safety functions and its overall performance should not be overly dependent on a single safety function.
4.1.5 The design, construction, operation and closure of the disposal site should be as passive as possible to ensure safety and the facility must be continuously
The need for active maintenance is minimized.
4.1.6 Site selection, construction, operation and closure activities should be carried out in a step-by-step manner and through the performance and safety of the disposal system.
Iterative design and evaluation provides support for each step of site selection, construction, operation, and shutdown.
4.1.7 In order to maintain the passive safety characteristics of the disposal site and ensure the safety function after the shutdown, the passive safety features of the disposal site should be monitored.
And control.
4.2 Radiation protection requirements for waste disposal
4.2.1 The radiation exposure of the disposal site to the staff and the public in normal operating conditions and accident conditions shall comply with the requirements of GB 18871.
begging.
4.2.2 The annual effective dose of radionuclides released to the environment by various means to a representative individual in the public does not exceed 0.25 mSv.
4.2.3 Provide protection to individuals who do not intend to break into the disposal site or contact the waste at any time after the disposition of the disposal of the disposal site,
The annual effective dose for unintentional intruders is no more than 1 mSv, and the effective dose for a single acute exposure does not exceed 5 mSv.
5 waste package
5.1 Waste body characteristics requirements
5.1.1 The activity concentration of radioactive solid waste disposed of near the surface shall comply with the provisions of the Classification of Radioactive Waste.
5.1.2 The content of non-corrosive free state liquid contained in solid waste should be as low as possible, and the volume of free liquid in the waste package should be less than solid.
1% of the volume of waste.
5.1.3 The following substances should not be included in the waste package.
a) Explosive or prone to severe decomposition or reaction at normal temperature and pressure, or a substance that reacts violently with water or air.
b) spontaneous combustion and flammable substances;
c) strong corrosive substances;
d) untreated animal carcasses and pathogen-containing substances;
e) non-radioactive highly toxic substances;
f) Toxic gases, vapours or fumes that contain or may have a detrimental effect on the transport, handling or disposal of workers.
5.1.4 The performance of cement cured body should meet the requirements of GB 14569.1. The performance of cement fixed waste body should meet the relevant requirements of EJ 1186
begging.
5.2 Waste package requirements
5.2.1 The waste packaging container shall comply with the provisions of GB 12711 and related standards, and shall meet the requirements for loading, unloading, transportation and disposal.
5.2.2 The waste contained in the waste packaging container should be as dense as possible and filled with the container.
5.2.3 The waste package should be stable, no structural damage will occur, and the disposal site will not be affected by the collapse or collapse of the waste package.
Overall stability. The stability of the waste package can be achieved by arranging the waste into a stable form or by charging the waste into a tall overall container.
5.2.4 The mark and logo of the waste package shall comply with the relevant provisions of GB 12711.
5.3 Waste package acceptance criteria
The operating organization of the disposal site shall be given the safety evaluation according to the requirements of 5.1 and 5.2, the environmental characteristics of the disposal site and the engineering measures adopted.
Waste acceptance criteria. Waste acceptance criteria should cover waste characteristics that are important to the safety of the disposal site and to safety after shutdown, including.
a) the type, characteristics and nuclide activity concentration of the waste packet;
b) the surface dose rate and surface contamination level allowed by the waste package;
c) the allowable range of chemical and physical properties of the waste;
d) substances not allowed in the waste;
e) the type of waste packaging container that can be received;
f) specifications for receiving waste packages;
g) quantitative requirements for quantitative measurement of waste characteristic measurement errors;
h) For the requirements of the waste package file, the contents of the waste package file are listed in Appendix A.
6 site selection
6.1 Site selection steps
6.1.1 Location phase division
The site selection of the disposal site can be divided into four stages. planning site selection, regional survey, site site evaluation and site determination.
6.1.2 Planning site selection
In the planning and site selection stage, the overall site selection plan should be established, the site selection principle should be established, and the required site characteristics should be determined.
6.1.3 Regional survey
Determining the area where it is possible to establish a disposal site, and the crustal structural stability, earthquake, geological structure, engineering geology, hydrology of the area
Geological, meteorological conditions and socio-economic factors are evaluated to determine possible sites.
6.1.4 Evaluation of site characteristics
Site characterization is based on regional surveys to determine recommended sites through on-site surveys, surveys, and analysis of data.
6.1.5 Site determination
Conduct a detailed study of the recommended site to demonstrate the suitability of the site and submit a detailed report to the regulatory authority to enable the regulatory department
Can make a judgment and approve the selected site.
6.2 Location criteria
6.2.1 General requirements
6.2.1.1 The location of the disposal site shall comply with the requirements of relevant national laws and regulations.
6.2.1.2 The site selection phase should consider the source of the waste package to be received at the site (total volume of waste and total activity of radioactivity) and future expansion of the disposal site.
The possibility.
6.2.2 Geology
6.2.2.1 The geological conditions of the site shall be conducive to the isolation of waste and the restriction of the migration of radionuclides to the outside world, and shall also be beneficial to the disposal system.
Stable, should provide sufficient space for disposal of waste.
6.2.2.2 Priority should be given to the uniformity of lithology, simple structure, good geological conditions, and easy identification of its characteristics by geological exploration techniques.
Site.
6.2.3 Hydrogeology
6.2.3.1 Site hydrogeological conditions should be conducive to blocking the migration of radionuclides.
6.2.3.2 Expected changes in important hydrogeological conditions due to natural events and disposal operations should be evaluated. Priority should be given to geological formation
A site that is simple, easy to evaluate hydrogeological properties and model.
6.2.3.3 The adsorption and dispersion characteristics of radioactive nuclides by groundwater systems should be evaluated.
6.2.3.4 The floor of the near-surface disposal unit should be above the groundwater level to prevent groundwater from entering the disposal unit.
6.2.3.5 The disposal site shall not be affected by the pollution of the water source. The distance between the site boundary and the water source shall be based on the radioactive core in the groundwater.
The migration evaluation of the prime is determined.
6.2.4 Geochemistry
6.2.4.1 The geochemical characteristics of groundwater and geological bodies shall be conducive to blocking the release of radionuclides from the disposal site and will not be significantly reduced.
The life of a low engineering barrier.
6.2.4.2 Priority should be given to geochemical chemistry that promotes the adsorption, precipitation/co-precipitation of radionuclides and the formation of easily transportable compounds.
Sexual site.
6.2.4.3 When considering possible chemical reactions in the treatment system, the following processes or parameters should be evaluated.
a) the erosion of groundwater to the engineering barrier;
b) chemical processes or conditions that affect the dissolution and adsorption of radionuclides;
c) the Eh value and pH value of groundwater;
d) chemical processes or conditions in which natural colloids and organic matter are present;
e) Disposal of gases that may be generated by the system.
6.2.5 Construction and earthquakes
6.2.5.1 The site should be selected in areas where tectonic activity and seismic activity are weak.
6.2.5.2 The following situations should be considered during the site selection process.
a) geological and historical evidence of active faults, tectonic activities or volcanic activity;
b) historical earthquake conditions, including magnitude and intensity;
c) the possibility of natural events that can cause changes in hydrogeological conditions;
d) Discrimination of sand liquefaction under earthquake action.
6.2.6 Surface effects
6.2.6.1 The frequency and intensity of surface activities such as floods, landslides and mudslides at the disposal site shall not affect the safety of the disposal system.
6.2.6.2 The disposal site should have good drainage capacity and should avoid flood-affected areas. Should evaluate precipitation, snow melting, water control structures
The impact of floods caused by failures, river blockages or landslides and debris flows on the disposal site should be minimized to prevent runoff erosion or flooding.
No. Priority should be given to areas or sites with good topographical and hydrological characteristics that can smoothly exclude floods.
6.2.7 Weather
6.2.7.1 The meteorological characteristics of the site area should be evaluated in order to take into account the effects of extreme meteorological conditions when designing the disposal site.
6.2.7.2 The likelihood of occurrence of extreme weather events should be assessed and the likely sites should be screened based on the extent of their impact. Site selection
Cheng should consider the following meteorological conditions.
a) precipitation (rain and snow);
b) Extreme weather phenomena.
6.2.8 Human events
6.2.8.1 Human activities, now or in the future, shall not affect the isolation capability of the disposal system in the vicinity of the identified site or site.
6.2.8.2 The impact of adjacent hazardous facilities or the possible disposal of dangerous goods on the disposal site should be assessed.
6.2.8.3 It should be checked whether there are potentially valuable mineral resources and other resources in the site area.
6.2.9 Waste package transportation
6.2.9.1 The site identified shall be convenient for transport of waste packages and the potential risks to the public shall be as low as possible.
6.2.9.2 Consideration should be given to the cost of transport of waste packages, normal transport and accidents.
6.2.10 Land use
6.2.10.1 The land use of the disposal site and the foreseeable land development and land use planning in the area should be considered.
6.2.10.2 The impact of the future use of land near the recommended site on the operation and performance of the disposal site should be evaluated, and disposal should also be considered.
The impact of the line on the future use of nearby land, such as restrictions on the future use of the land.
6.2.11 Population distribution
The disposal site should avoid densely populated areas, and should consider the possibility of future interference of the disposal site, as well as the radioactive nucleus released by the disposal site.
Radiation effects on the public.
6.2.12 Environmental protection
It should be ensured that the surrounding environment is adequately protected during the life of the disposal site and that the possible adverse effects are reduced to an acceptable level.
7 Design and construction of the disposal site
7.1 General requirements
7.1.1 The design of the disposal site shall meet the requirements of Chapter 4 of this standard.
7.1.2 The design of the disposal site shall provide the necessary conditions for the closure of the disposal site.
7.1.3 Natural barriers should be fully utilized and engineering barriers should be placed to ensure and enhance the containment and isolation functions of the disposal site.
7.1.4 Radiation protection of the disposal site should be carried out according to the disposal process, radiation protection practices, estimated radiation exposure and the possibility of contamination.
Optimized design.
7.1.5 The disposal site shall set up personal dose monitoring equipment and regional monitoring equipment according to the radiation protection requirements, according to the disposal unit and waste package.
Sexual design waste monitoring equipment, radiation monitoring design of the disposal site should also meet the monitoring needs of normal operation and accident conditions.
7.2 Design of the disposal site
7.2.1 Determine the design disposal capacity of the disposal site, including the volume of the waste package, through a safety full-process system analysis based on the specific site characteristics.
Total activity. The disposal site is generally composed of a disposal unit area, a waste collection station, a laboratory, a garage, and the like. The design of the disposal unit area should be based on the audience
The overall plan is arranged. The overall plan of the disposal site should pay attention to the arrangement of the inlet and the passage, as well as the radioactive operation area and the non-radioactive operation area.
control.
7.2.2 The waste receiving station can be set according to the actual situation of the disposal site.
a) waste pack surface dose rate, surface contamination, nuclide activity, appearance quality, and inspection devices for transport vehicles and transport containers;
b) loading and unloading equipment for waste packages;
c) transportation vehicle access radiation monitoring and alarm equipment;
d) the means of handling the accidental damage to the waste package when generating secondary waste and disposal;
e) Decontamination means for transport vehicles.
7.2.3 For disposal sites that receive high surface dose rate waste packages, equipment for remote or remote transport and placement of waste packages should be provided.
7.2.4 The design of the waste disposal unit may be based on the above-ground mound type, underground trench type and other forms to adapt to different site characteristics and not
Disposal requirements for the same type of waste. The disposal unit shall be designed for seismic ...
Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB 9132-2018_English be delivered?Answer: Upon your order, we will start to translate GB 9132-2018_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 9132-2018_English with my colleagues?Answer: Yes. The purchased PDF of GB 9132-2018_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 9132-2018?Answer: Yes. Unless special scenarios such as technical constraints or academic study, you should always prioritize to purchase the latest version GB 9132-2018 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.
|