|
US$319.00 · In stock
Delivery: <= 4 days. True-PDF full-copy in English will be manually translated and delivered via email.
GB 23727-2020: Regulations for radiation protection and radiation environment protection in uranium mining and milling
Status: Valid GB 23727: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB 23727-2020 | English | 319 |
Add to Cart
|
4 days [Need to translate]
|
Regulations for radiation protection and radiation environment protection in uranium mining and milling
| Valid |
GB 23727-2020
|
| GB 23727-2009 | English | 639 |
Add to Cart
|
3 days [Need to translate]
|
Regulations for radiation and environment protection in uranium mining and milling
| Obsolete |
GB 23727-2009
|
PDF similar to GB 23727-2020
Basic data | Standard ID | GB 23727-2020 (GB23727-2020) | | Description (Translated English) | Regulations for radiation protection and radiation environment protection in uranium mining and milling | | Sector / Industry | National Standard | | Classification of Chinese Standard | F73 | | Word Count Estimation | 17,125 | | Date of Issue | 2020-10-11 | | Date of Implementation | 2020-12-01 | | Older Standard (superseded by this standard) | GB 23727-2009 | | Regulation (derived from) | Ministry of Ecology and Environment Announcement No. 35 (2020) | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB 23727-2009: Regulations for radiation and environment protection in uranium mining and milling
---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 and environment protection in uranium mining and milling
ICS 13.280
F73
National Standards of People's Republic of China
URANIUM radiation protection and environmental protection provisions
Posted 2009-05-06
2010-02-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Foreword
All the technical contents of this standard is mandatory.
The standard proposed by China National Nuclear Corporation.
This standard by the National Standardization Technical Committee on Nuclear Energy (SAC/TC58) centralized.
This standard was drafted. Nuclear Industry Beijing Research Institute of Chemical Engineering and Metallurgy.
The main drafters of this standard. Lixian Jie, Deng Wenhui INTERNATIONAL JOURNAL Xu Lechang.
URANIUM radiation protection and environmental protection provisions
1 Scope
This standard specifies the uranium mining and milling plant siting, design, construction, operation, closure or decommissioning process to be followed and radiation protection ring
Environmental protection principles and basic requirements.
This standard applies to uranium mines and uranium dressing plant. Containing uranium (thorium) associated minerals mining or dressing plant can be implemented by reference.
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/T 4960.3 term nuclear fuel and nuclear science and technology of nuclear fuel cycle
GB/T 4960.5 nuclear science and technology terminology Radiation Protection and Safety of Radiation Sources
GB/T 4960.8 nuclear science and technology - Part 8. Radioactive Waste Management
GB 11216 General requirements for nuclear facility effluent and environmental radioactivity monitoring quality assurance program
GB 11806 Regulations for the Safe Transport of Radioactive Substances
GB 12379 environmental radiation monitoring provisions
GB 14586 environmental management of decommissioning of uranium mining and milling facilities technical requirements
GB 18871-2002 ionizing radiation protection and safety of radiation sources basic standards
3 Terms and Definitions
GB/T 4960.3, GB/T 4960.5, GB/T 4960.8 and GB 18871 and established the following terms and definitions apply to this
standard.
3.1
Mining containing uranium series or thorium series radionuclides ore beneficiation and hydrometallurgical process for short or processing activities.
3.2
For the evaluation and control of radiation or radioactive material irradiation, measurement and interpretation of the results of the measurement of dose or contamination carried out.
3.3
Radiation monitoring in the environment outside the facility boundaries source carried out.
3.4
Uranium produced in the mining process can be used reach ore rocks, including on human health or the environment does not have a significant radiation risk
Harmful waste rock and mineralized having a chemical or radiological characteristics of the waste rock.
3.5
To extract uranium from ore crushing residues from processing, including residues generated during hydrometallurgical processing and heap leach ore and produce
Residue.
3.6
Also known as uranium ore concentrate (uraniumoreconcentrate), physical or chemical processing of uranium ores and other materials prepared containing uranium
Obtained with high uranium content of the crude product, including diuranate or uranium salt form, commonly known as yellowcake.
3.7
The ore or ore crushing or granulated sheet after deposited on the natural or artificial impervious substrate, the solution infusion solution is sprayed onto the reactor building
Ore above selectively dissolving the ore in the useful component, after infiltration leaching, the leachate collection process.
3.8
The solution infusion solution is injected through the injection drilling fluid having a suitable permeability with seam, the seam permeability and diffusion containing dissolved minerals
The useful component, and then drilling or other channels leachate collection process by pumping liquid.
3.9
The ore in the mine stope blasting or other methods to control the build-place pile crushing, the ore is dissolved infusion solution is sprayed onto the top of the heap have built
Selectively dissolving the ore in the useful components, infiltrated leaching, the leachate collection process.
3.10
The proposed radioactive liquid waste discharged before the injection tank, the detection of its activity concentration, when the concentration is below the limit before discharge emission management, and
Recording emissions and emission concentrations when the concentration is higher than the limit of emissions management, must not be discharged, to return to its reprocessing until the concentration is lower than tube
One way to manage limits.
3.11
Uranium mining and milling facilities after the end of the lifetime of use or other reasons to stop service, taking full account of the protection of workers and the public health and safety and
The various activities carried out under the premise of protecting the environment.
3.12
Underground mine equipment, wellhead industrial sites, waste rock and tailings (residue) library to leaching field, milling equipment and other facilities to stop using.
3.13
Used by a single shipper alone of a conveyance or of a large freight container, and in accordance with the requirements of the shipper or consignee
Transportation, including the starting point, intermediate and final loading and unloading.
3.14
Or one α potential exposure of Rn-220 progeny of radon progeny non-SI units. A working level month (WLM) is a work
Level (1L air any combination of radon progeny or Rn-220 progeny, they will eventually emit α particle energy of 1.3 × 105 MeV)
Concentration continuously irradiated 170h. Relationship with SI units is. 1WLM = 3.5 × 10-3J · h/m3.
4 basic requirements for radiation protection and environmental protection
4.1 Uranium mining and milling plant siting, design, construction, operation, closure and decommissioning practices should be in accordance with relevant regulations and standards into
OK, radiation protection and environmental protection in line with the relevant requirements of the regulatory department under.
4.2 URANIUM production practice, should follow the practice of legitimacy, protection and safety of optimization, dose constraints and about the risk of potential exposure
Beam requirements.
4.3 URANIUM new construction, expansion, renovation and decommissioning project environmental impact assessment should be carried out in accordance with relevant regulations.
4.4 Uranium Mining and construction, expansion, radiation protection and pollution control facilities renovation project should be implemented simultaneously with the main project designed, constructed,
And put into use the "three simultaneous" requirement. Uranium mining and milling waste treatment should be combined with the production process of reform, technological innovation, utilization, achieve
Waste minimization.
4.5 URANIUM business from start to finish should focus on ecological protection, the abandoned stripped topsoil, waste rock, tailings and residues should be disposed of in a concentrated
Specially designated area, shall be dumped to rivers, lakes, reservoirs and outside specially designated places ditches; mining or construction of the vegetation is damaged,
Measures should be taken to rehabilitate the topsoil and vegetation to prevent soil erosion.
4.6 In the case of continuous exposure, unless the uranium mining and milling facilities resulting in public housing and their workplaces for radon (Rn-222) concentration exceeds
GB 18871-2002 action level specified in Annex H, or generally do not need to take remedial action.
4.7 URANIUM enterprise shall determine the measures and resources to implement radiation protection and environmental protection objectives required for the establishment of radiation protection, environmental protection
And emergency management agencies, with professional and technical personnel; the implementation of national and industry (the bureau) issued by the relevant radiation protection and environmental regulations
And regulations, strengthen the leadership of radiation protection, radiation protection and emergency work; and to ensure proper implementation of these measures and to provide these resources
Source; keep such measures and resources, regular review, and regularly verify whether its objectives are achieved.
4.8 URANIUM enterprises should cultivate and maintain good radiation protection and cultural quality of environmental protection, the development of radiation protection and environmental protection outline,
Specifically those responsible for radiation protection and environmental protection; establish personal responsibility radiation protection, environmental protection and emergency management
Rules and regulations of the education and training system, operating procedures, and data archiving system, reporting system, etc., radiation protection authorities should monitor implementation.
4.9 uranium mining and milling factories, mines and enterprises should be based on the type of production scale, length of service, and radiation monitoring tasks set radiation (dose) or radiation protection chamber
Protection (monitoring) stations. Radiation protection (dose) of radiation monitoring stations room or undertake workplace and environmental radiation monitoring units, the survey of pollution sources,
Personal dose monitoring, and emergency management and other work. According to sources of radiation monitoring and investigation units and other tasks and requirements, complete with radiation
Monitors and equipped with radiation monitoring equipment.
4.10 URANIUM enterprise shall, in accordance with the relevant provisions to the requirements of the regulatory authorities or the competent authorities to submit the relevant monitoring radiation protection and environmental protection
Test data and related information.
4.11 in radiation protection, environmental protection and emergency management personnel should have appropriate qualifications, and education, training and regular assessment.
For all staff involved in the activities of the occupational exposure of radiation safety carried out pre-job education and training.
5 dose limiting
5.1 dose limit
5.1.1 uranium mining and milling of occupational dose limits shall comply with Appendix B of B. GB 18871-2002 1.1 provisions.
Practice with radiation exposure 5.1.2 uranium mining, dressing and smelting plant, and other members of the public by dose exposure limits should be consistent with GB 18871-
B. 2002 in Appendix B 1.2 provisions.
5.2 dose constraint value
5.2.1 uranium mining and milling companies should develop their practice due to the dose constraint value occupational and public exposure according to the ALARA principle,
And shall be approved by the regulatory authorities.
Under a) In general, the dose constraint value of occupational exposure to take five consecutive years, the average annual effective dose does not exceed 15mSv/a;
Dose constraint value b) public exposure to take five consecutive years, the average annual effective dose does not exceed 0.5mSv/a;
Under c) special circumstances, the dose constraint value of occupational exposure may be greater than 15mSv/a, but shall not exceed the dose limit 20mSv/a.
5.2.2 consider URANIUM both by γ external beam irradiation but also by the special nature of radon and uranium-based long-lived radionuclides α aerosols, which spoke
Shot dose should meet the requirements of the formula (1).
DL +
IRnD
IRnD, L +
Iα
Iα, L ≤
1 (1)
Where.
DL --- corresponding effective dose of annual dose constraint value in units of mSv [Waters] (mSv);
IRnD --- inhaled radon progeny α potential intake in units of coke [ear] (J);
Iα --- inhaled uranium-based long-lived radionuclides α aerosol annual intake unit is becquerel [Harrell] (Bq);
IRnD, L --- inhaled radon progeny α potential annual intake constraint value in units of coke [ear] (J);
Iα, L --- inhaled uranium-based long-lived radionuclides α aerosol annual intake constraint value in units of becquerels [Harrell] (Bq).
5.3 limit of intake
According to Appendix B of B. GB 18871-2002 1.3.4 provides that, in the case without considering other exposure, occupational exposure Table 1 gives
Corresponding intake suction radon (Rn-222) or Rn-220 and uranium-based sub-body long-lived radionuclides α aerosol constraint value.
5.4 Export concentration
5.4.1 In considering working time is 2000h, without considering other irradiation conditions, Table 2 shows the values of dose limits and dose constraints
Exporting uranium mining and metallurgy radiation in the workplace main radionuclides derived air concentration (DAC).
5.4.2 Export concentration reference value only to the design, management and monitoring of convenience given, according to the work required, to allow one or more times
Inhalation of radioactive substances in the air exceeds a predetermined concentration 5.4.1, but inhalation of radioactive substances within one year shall not exceed the annual intake of constraints
Value Ij, inh, L.
5.4.3 For residential radon and uranium mining and milling facilities due to continuous exposure of non-radioactive occupation in the workplace and its action level optimization should meet
Co GB 18871-2002 Annex H requirements.
Table 1 intake limits and constraint values
The type of radionuclide intake of constraint values
Occupational exposure
Rn-222 progeny α potential intake (exposure) a 0.013J (3WLM)
Rn-220 progeny α potential intake (exposure) b 0.038J (9WLM)
Uranium-based long-lived radionuclides α aerosol intake c 2140Bq
A conversion factor of occupational exposure Rn-222 progeny use of 1.4mSv/(mJ · h · m-3), respiratory rate of 1.2m3/h;
Occupational exposure conversion coefficient b Rn-220 progeny use of 0.47mSv/(mJ · h · m-3), respiratory rate of 1.2m3/h;
c. For natural uranium-based occupational exposure consider five long-lived α radionuclides is in radioactive equilibrium state; inhalation dose conversion factor (Sv/Bq) were
(238U) 7.30 × 10-6, (234U) 8.50 × 10-6, (230Th) 1.30 × 10-5, (226Ra) 3.20 × 10-6, (210Po) 3.00 × 10-6.
Table 2 derived air concentration
project
222Rn daughters
μJ/m
222Rn
Bq/m3
Uranium-based long-lived radionuclides α aerosols
Bq/m3
Natural uranium aerosols α
Bq/m3 or (mg/m3)
Dose limits 7.1 3700a 1.2b 1.0c or (0.04)
Dose constraint value 5.4 2700a 0.9b 0.8c or (0.03)
consider a uranium mine equilibrium factor of 0.35;
b consider uranium series 5 long-lived α radionuclides is in radioactive equilibrium; inhalation dose conversion factor (Sv/Bq), respectively (238U), 7.30 × 10-6,
(234U) 8.50 × 10-6, (230Th) 1.30 × 10-5, (226Ra) 3.20 × 10-6, (210Po) 3.00 × 10-6;
c only consider 238U, 234U and 235U natural abundance contribution to dose.
5.5 surface contamination control level
5.5.1 Workplace (not including underground workplace) table, equipment, walls, floors, roof surface as well as staff, work clothes,
Radioactive pollution control underwear surface materials shown in Table 3.
When workplace equipment, walls, floors, roofing appropriate decontamination measures, still exceeds the values in Table 3 are listed, it can be regarded as fixity
Pollution. After examination and administration department or the department authorized by the regulatory authorities to check it agrees, an appropriate increase in the level of control, but not more than listed in Table 3
5 times the value.
5.5.2 workplace equipment, decontamination supplies after treatment, the level of contamination is reduced to values listed in Table 3, the control region one fiftieth
Or less, by the regulatory authorities or the department authorized by the regulatory authorities confirm consent, can be used as common items to use.
5.6 effluent concentration limits
5.6.1 dilution capacity of the receiving water, the concentration of each radionuclide emissions should waste water discharge and the discharge port at the downstream of the first drinking water intake point
In line with the requirements of Table 3; no dilution capacity of the receiving water body, each radionuclide emission concentration in waste water discharge point shall conform to the requirements of Table 4.
5.6.2 Central Africa radioactive effluent concentration of harmful substances shall execute the relevant national or local standards.
Radiation protection and environmental protection principles 6 Siting and Design
6.1 General principles of site selection
Table level radioactive surface contamination control unit for 3 workplaces Bq [Harrell] per square centimeter (Bq/cm2)
Radioactive contamination of the surface type α β radioactive substance
Table, equipment, floors, walls
Room hydrometallurgical plant, laboratories, machine repair, and other inter-like pieces 440
Shower room, the dosing chamber, air compressor room, machine room ventilation, etc. 0.4 4
Overalls, gloves, work shoes 0.4 4
Hand, skin, underwear, socks work 0.04 0.4
Note 1. The high-pollution except sub-regions in the region.
Note 2. Total fixed contamination means contamination and loose values listed in the table.
Note 3. hands, skin, underwear, socks contaminated work, should be cleaned as much as possible to clean the background level. Other than listed in the table surface contamination levels
Data, decontamination measures should be taken.
Note 4. The surface level of pollution control a certain area on the mean value calculation. skin, clothes, etc. take 100cm2, equipment take 300cm2, ground
Take 1000cm2.
Note 5. β particle energy is less than the maximum 0.3MeV, surface contamination control level radioactive material is five times the values listed in the table.
Table 4 radionuclide emission concentration limits
Water environment of radioactive material or nuclide unit waste water discharge limits at the first point of water limits
Dilution capacity of the receiving water body
(5 times dilution)
U mg/L 0.3 0.05
Ra-226 Bq/L 1.1 1.1
Th-230 Bq/L 1.85 1
Pb-210 Bq/L 0.5 0.1
Po-210 Bq/L 0.5 0.1
Not receiving water by
U mg/L 0.05
Ra-226 Bq/L 1.1
Th-230 Bq/L 1
Pb-210 Bq/L 0.1
Po-210 Bq/L 0.1
Note. each radionuclide emission trough concentration data meets the requirements listed in the table, its concentration monitoring should be considered for fast measurement time; U should be monitored every slot.
6.1.1 In selecting the construction site of uranium mining and milling facilities, must consider the sources of uranium mining and milling facilities, the geographic environment in the region, transportation and raw
State conditions, hydrology and hydrogeology, geology and geological structure, weather, natural disasters, socio-economic, industrial and mining enterprises distribution, land use and planning
And other conditions, and ecological function protected areas, nature reserves, scenic spots, drinking water source protection areas, protected forest areas, grasslands protected areas,
Provision of basic farmland protection areas and other relevant state laws and regulations, after a comprehensive analysis, feasibility studies, to make a choice after comparison.
6.1.2 should consider uranium mining and milling facilities during normal operation and under accident conditions, the release of radioactive effluents to the environment and the public caused by
The long-term effects, doses to the public in line with the requirements of 5.1.2 and 5.2.1 and to meet the principles as low as reasonably achievable. Unexpected things
By limiting the members of staff and members of the public suffered exposure size and the possibility to as low as reasonably achievable level.
6.1.3 should be based on local natural resources, development planning and the natural environment, giving priority to construction near the mine, but the main building structures, heap leaching field
And tailings (residue) libraries should not be built in the mining sphere of influence, or should take measures to prevent the impact of mining activities on each other's facilities.
The proposed plant (field) site, waste rock and tailings (residue) library and ventilation wells should be selected in a low population density, radioactive effluent dilution and dispersion conditions
Good location, farmland should be minimal and should not be built in the river. Waste rock, tailings, tailings and other organizations should focus stacking, to prevent the loss, easy
Decommissioning final disposal.
When choosing the location of waste rock and tailings (residue) library, in addition to meeting the above requirements, we must also consider their safety, stability, discharge capacity, and
Close conducive environment management after retirement. From the hydrological, geological, seismic and other considerations does not meet the requirements should not be long-term stability as a storage site.
6.1.4 When selecting URANIUM field (factory) site, waste rock and tailings (residue) library and other locations, should be more than Alternatives, safety analysis, environment
Impact analysis and optimization analysis, after a comprehensive assessment chosen as demonstration.
6.2 General principles of design
6.2.1 uranium mining and milling facilities should be based on the overall arrangement of the pollutants discharge its production run, combined with local meteorology, hydrology, topography,
And other natural conditions and population distribution, reasonable layout of production area and living area. Both the relative concentration of each facility arrangement should also be in line with anti-radiation
Protection requirements, to avoid contamination between them.
6.2.2 Depending on the nature of uranium mining and milling facilities, the scale of radioactive effluent discharge status and local terrain conditions, living area all year round should be local
Less frequent wind direction is arranged in the uranium mining and milling major sources (tailings, ventilation wells) of the downwind side, the separation distance not less than 800m,
Not meet the requirements for approval shall be approved by the relevant examination and administration department.
6.2.3 tailings (residue) library, open pit, ventilation and other wellhead separation distance from the boundary of the residential area not less than 800m, in the mountains or body apart
After take certain protective measures, the separation distance can be appropriately reduced.
Boundary spacing distance from residential areas wellhead industrial sites, dressing and smelting plant, laboratory, ore bin, heap leaching field, waste rock, etc. should not be less than 300m.
Tailings (residue) library, open pit, heap leach fields, waste rock and other facilities open-air boundary spacing distance from the source of drinking water should not be less than 500m.
Do not meet the spacing requirements of the uranium mining and milling facilities, shall be approved by the examination and administration department.
6.2.4 uranium ore mining, preselected, hydrometallurgy should adopt appropriate processes and equipment, so that the minimum amount of waste generated, reducing URANIUM
"Three wastes" emissions and reduce the number of radionuclide activity concentration.
6.2.5 URANIUM production process generated waste water, waste gas, waste should be taken to disposal or treatment of advanced and effective measures to reduce the ring
Environmental impact, and meet the requirements of 5.1.2 and 5.2.1.
a) mining waste rock, or tailings (residue) should be given priority backfill program. Waste rock pile should focus on waste rock, waste rock should be taken to prevent water
Measures of soil loss.
b) tailings (residue) library should give priority to large capacity, small catchment area, a small amount of dam construction program. It should not occupy less accounted for farmland. dam
Reservoir site and should avoid adverse geological formations (such as landslides, cave, faults and landslides). Reservoir should be selected in the fissure is not developed and possessed
Natural impermeable layer formation regions, seepage or should take measures to reduce tailings, heap leach residue impact on groun...
Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB 23727-2020_English be delivered?Answer: Upon your order, we will start to translate GB 23727-2020_English as soon as possible, and keep you informed of the progress. The lead time is typically 2 ~ 4 working days. The lengthier the document the longer the lead time. Question 2: Can I share the purchased PDF of GB 23727-2020_English with my colleagues?Answer: Yes. The purchased PDF of GB 23727-2020_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 23727-2020?Answer: Yes. Unless special scenarios such as technical constraints or academic study, you should always prioritize to purchase the latest version GB 23727-2020 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.
|