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HJ 1114-2020 English PDF

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HJ 1114-2020: Technical specifications of radiation environmental protection for other radioactive material’s storage and solid waste’s landfill (Trial)
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Standard ID	Contents [version]	USD	STEP2	[PDF] delivered in	Standard Title (Description)	Status	PDF
HJ 1114-2020	English	209	Add to Cart	3 days [Need to translate]	Technical specifications of radiation environmental protection for other radioactive material’s storage and solid waste’s landfill (Trial)	Valid	HJ 1114-2020

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Basic data

Standard ID	HJ 1114-2020 (HJ1114-2020)
Description (Translated English)	Technical specifications of radiation environmental protection for other radioactive material��s storage and solid waste��s landfill (Trial)
Sector / Industry	Environmental Protection Industry Standard
Word Count Estimation	9,945
Date of Issue	2020
Date of Implementation	2020-04-01
Issuing agency(ies)	Ministry of Ecology and Environment

HJ 1114-2020: Technical specifications of radiation environmental protection for other radioactive material’s storage and solid waste’s landfill (Trial)

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Technical specifications of radiation environmental protection for other radioactive material's storage and solid waste's landfill (Trial) Storage of associated radioactive materials and landfill of solid waste Technical Specifications for Radiation Environmental Protection (Trial) National Environmental Protection Standards of the People's Republic of China 2020-03-03 release 2020-04-01 Implementation Issued by the Ministry of Ecology and Environment

Foreword...ⅱ 1 Scope of application...1 2 Normative references...1 3 Terms and definitions...1 4 General...1 5 Site selection...2 6 Design and Construction...2 7 Operation...3 8 Close...4 9 Monitoring...4 10 Radiation Monitoring...4

Foreword

To implement the Environmental Protection Law of the People’s Republic of China and the Law of the People’s Republic of China on the Prevention and Control of Radioactive Pollution, strengthen the Radiation environment management for storage of sexual materials and solid waste landfill, prevention and control of radioactive pollution, protection of the ecological environment and public radiation safety, Develop this standard. This standard specifies rare earth, niobium/tantalum, zirconium and zirconium oxide, tin, lead/zinc, copper, steel, vanadium, phosphate, coal, aluminum, molybdenum, nickel, The storage of radioactive materials associated with the development and utilization of non-uranium (thorium) mineral resources such as germanium, titanium, gold and solid waste landfill facilities are Radiation environmental protection principles and general technical requirements that should be followed in the process of planning, construction, operation, shutdown, and monitoring. Other non-uranium (thorium) minerals Resources development and utilization activities can be implemented by reference. This standard is issued for the first time. This standard is organized and formulated by the Department of Radiation Source Safety Supervision of the Ministry of Ecology and Environment. Drafting organization of this standard. China Nuclear Fourth Research and Design Engineering Co., Ltd. This standard was approved by the Ministry of Ecology and Environment on March 3, 2020. This standard will be implemented on April 1, 2020. This standard is interpreted by the Ministry of Ecology and Environment. Technical specifications for radiation environmental protection of associated radioactive materials storage and solid waste landfill (Trial)

1 Scope of application

This standard specifies rare earth, niobium/tantalum, zirconium and zirconium oxide, tin, lead/zinc, copper, steel, vanadium, phosphate, coal, aluminum, molybdenum, nickel, The storage of radioactive materials associated with the development and utilization of non-uranium (thorium) mineral resources such as germanium, titanium, gold and solid waste landfill facilities are Radiation environmental protection principles and general technical requirements that should be followed in the process of planning, construction, operation, shutdown, and monitoring. Other non-uranium (thorium) minerals Resources development and utilization activities can be implemented by reference. Uranium (thorium) is a single nuclide activity concentration greater than 400Bq/g associated radioactive material storage and solid waste disposal, should be based on actual conditions The situation takes more stringent environmental protection measures.

2 Normative references

This standard quotes the terms in the following documents. For undated reference documents, their valid versions are applicable to this standard. GB 18871 Basic standard for ionizing radiation protection and radiation source safety GB 23727 Regulations on Radiation Protection and Environmental Protection of Uranium Mining and Metallurgy HJ/T 61 Technical Specification for Radiation Environmental Monitoring

3 Terms and definitions

The following terms and definitions apply to this standard. 3.1 Other radioactive material Uranium (thorium) used or produced in the development and utilization of non-uranium (thorium) mineral resources is a raw ore with a single nuclide activity concentration exceeding 1Bq/g Intermediate products, tailings, tailings and other residues, etc. 3.2 Other radioactive solid waste Uranium (thorium) produced in the development and utilization of non-uranium (thorium) mineral resources is a solid waste with a single nuclide activity concentration exceeding 1Bq/g, Including tailings, tailings and other residues produced during mining and smelting.

4 General

4.1 Basic principles 4.1.1 The process of design, construction, operation and closure of associated radioactive material storage facilities, site selection, design, etc. of solid waste landfill facilities The construction, operation, closure, guardianship and other processes shall be carried out in accordance with relevant laws, regulations and standards. 4.1.3 The radioactive pollution prevention and control facilities that need to be built as supporting facilities for the development and utilization of associated radioactive mines in new, reconstruction and expansion projects shall be The main project is designed, constructed and put into production at the same time. 4.1.4 The associated radioactive ore development and utilization unit can construct the associated radioactive solid waste landfill facility by itself in accordance with this technical specification, or The associated solid radioactive waste is sent to the landfill facilities of other units for landfill. Encourage the use of uranium mining and metallurgical facilities to landfill associated solid radioactive waste. 4.1.5 The associated radioactive mine development and utilization unit shall carry out source control and recycling of waste to minimize waste and adopt engineering measures. And technical measures to ensure that the effluent meets the discharge standards. 4.1.6 Measures should be taken during the site selection, design, construction, operation, closure, and monitoring of associated solid radioactive waste landfill facilities to ensure Long-term safety and stability of barrier facilities. 4.2 General requirements 4.2.1 The associated radioactive materials should be stored separately from other materials. 4.2.2 The associated solid radioactive waste should be landfilled in time; if there are no landfill conditions, special facilities should be built for storage. 4.2.3 Encourage the recycling and utilization of valuable resources in associated solid radioactive waste to minimize waste; for uranium content up to 0.1% of solid waste should be recycled and reused as uranium resources. 4.2.4 The storage and landfill of associated solid radioactive waste should implement a ledger system. 4.2.5 The development and utilization unit of associated radioactive minerals shall implement relevant laws, regulations and standards issued by the state and industry, and provide necessary Manpower, material resources and other safeguard measures; establishment of radiation environment management institutions, with professional technicians and management personnel; establishment of radiation environment management posts Position responsibility system, education and training system, reporting system, etc. 4.2.6 If the associated solid radioactive waste has the characteristics of hazardous waste at the same time, its storage and landfill shall also meet the requirements of relevant technical standards for hazardous waste.

5 Site selection

5.1 The landfill facility site should meet the relevant requirements of the national and local ecological environment function zoning, land and space planning, etc. 5.2 The site of landfill facilities is preferentially selected in areas with relatively low population density and far away from drinking water sources; according to the public dose constraint value Requirements, natural environmental conditions and other factors, determine the distance between the site and environmentally sensitive targets through environmental impact assessment. 5.3 The landfill facility site should have good regional stability and rock and soil stability, no spring water exposed, low permeability, and resistance to radionuclides. Has better blocking performance. 5.4 The bottom of the foundation layer of the landfill facility site should be kept at a distance of more than 3m from the highest water level since the record of the groundwater. Measures such as drainage or improve the design standards of anti-seepage. 5.5 The landfill facility site should avoid active fault zones, and avoid being built in karst cave areas or vulnerable to floods, landslides, mudslides, and unsteady alluvial deposits. Areas affected by surface action such as fans and gullies. 5.6 The landfill facility site should be located above the water level of the once-in-a-hundred-year flood with the return period not less than, and outside the planned water conservancy facility inundation area and protection area.

6 Design and construction

6.1 Design requirements for storage facilities for associated radioactive materials 6.1.1 The storage facilities should be arranged as far away from crowd activities as possible according to the general layout of the enterprise and other relevant requirements. 6.1.2 Physical isolation measures should be taken in storage facilities to prevent unrelated persons from entering. 6.1.3 The storage facilities should be cleaned and diverted to prevent rainwater from entering; where the material may seep water should be set up with drainage and other seepage collection systems, Seepage water should be recycled or treated and discharged in compliance with standards. 6.1.4 The storage facilities should be designed for anti-corrosion and anti-seepage, and the anti-seepage performance should not be lower than the clay layer with a permeability coefficient of 1×10-7cm/s and a thickness of 2m. The anti-seepage effect. 6.1.5 Dust prevention and dust suppression measures shall be taken for material storage to prevent the material from escaping. 6.1.6 A reasonable storage area shall be divided according to the source of the material and the level of radioactivity. 6.2 Design requirements for landfill facilities of associated solid radioactive waste 6.2.1 The design of landfill facilities should aim to achieve effective separation of waste from the biosphere. 6.2.2 The overall layout should take into account the local weather, hydrology, topography and other natural conditions and the surrounding population distribution, and rationally arrange the landfill area and office The public area and office area should be arranged in the downwind direction of the area with the smallest wind frequency throughout the year. 6.2.3 The landfill facilities should be equipped with anti-seepage system, flood interception and drainage system, etc., and set up seepage diversion system, groundwater diversion system, etc. according to the actual situation. Wastewater treatment system, etc. 6.2.4 The anti-seepage system of landfill facilities is mainly composed of natural foundation layer, natural material anti-seepage layer and double artificial anti-seepage lining, which should meet the following requirements. a) The permeability coefficient of the natural base layer should not be more than 1×10-5cm/s, and the thickness should not be less than 2m. b) An anti-seepage layer of natural material should be set between the natural base layer and the double artificial anti-seepage lining, the permeability coefficient is not more than 1×10-7cm/s, and the thickness It should be determined according to the characteristics of natural radionuclides and the blocking performance of natural materials impermeable layers. c) The dual artificial anti-seepage lining is composed of a primary lining, a protective layer of the primary lining and a secondary lining. The permeability coefficients of the primary and secondary linings are not greater than 1×10-12cm/s, The thickness is not less than 2.0mm; the protective layer of the main lining should be a clay lining with a permeability coefficient not greater than 1×10-7cm/s and a thickness not less than 0.3m. 6.2.5 The seepage drainage system of landfill facilities is composed of seepage drainage layer, collection and drainage pipes and water collection wells; the drainage layer should be made of natural materials, The slope should not be less than 2%. 6.2.6 A leakage detection layer (also serving as a drainage layer) should be set between the two artificial anti-seepage linings, and the guiding and drainage medium between the two artificial anti-seepage linings, The collection and drainage pipeline and the collection well; the permeability coefficient of the detection layer should not be less than 0.1cm/s. 6.2.7 Groundwater monitoring wells should be set at the upstream and downstream of the landfill facility, and groundwater monitoring wells should be set on both sides. 6.2.8 Intermediate coverage and closure coverage of landfill facilities should be carried out according to actual operation conditions. The closure design should meet safety, stability and radiation Shielding requirements. 6.2.9 The closing structure of landfill facilities shall include radon (thorium) shielding layer (also serving as natural impermeable layer), artificial impermeable lining, drainage layer, The material intrusion layer and vegetation restoration layer shall meet the following requirements. a) Radon (thorium) shielding layer. Natural materials are used, the permeability coefficient is not more than 1×10-7cm/s, and the thickness should be based on the diffusion of radon (thorium) The characteristics and material shielding performance are determined. b) Artificial anti-seepage lining. the permeability coefficient is not more than 1×10-12cm/s, and the thickness is not less than 1.5mm. c) Drainage layer. the permeability coefficient is not less than 0.1cm/s. d) Anti-biological intrusion layer. pebble layer with a thickness of not less than 30cm. e) Vegetation restoration layer. the thickness is not less than 35cm, and the vegetation should not damage the seepage prevention layer. 6.3 The storage of associated radioactive materials and the landfill of solid wastes shall take necessary radiation protection measures according to the level of radioactivity. 6.4 Corresponding radioactive pollution prevention and control measures shall be taken in the process of the storage of associated radioactive materials and the reconstruction and expansion of solid waste landfill facilities. 7 Run 7.1 Operation requirements of associated radioactive material storage facilities 7.1.1 Signs of ionizing radiation should be set up at obvious locations on the boundary of storage facilities, and management should be strengthened to prevent entry of irrelevant personnel. 7.1.2 The storage of solid waste shall be clearly marked, and the name, quantity, and activity concentration of radionuclide of the waste shall be indicated in accordance with the actual situation. 7.1.3 The solid waste storage ledger shall indicate the name, source, quantity, radionuclide activity concentration, storage date, Information such as the date of delivery and the name of the receiving unit. 7.1.4 The waste water treatment facilities and dust-proof and dust-suppression measures supporting the storage of materials shall be operated stably and effectively implemented. 7.2 Operation requirements of landfill facilities for associated solid radioactive waste 7.2.1 Acceptance criteria a) The solid waste should be neutralized and stabilized before landfill to reduce the radionuclide leaching performance. d) Solid wastes with unclear marks or unknown sources shall not enter the landfill facility. e) It is strictly forbidden to mix artificial radioactive waste and non-radioactive waste in the landfill facility. 7.2.2 The operation of landfill facilities shall meet the relevant requirements of 7.1.1, 7.1.3 and 7.1.4 at the same time.

8 Close

8.1 After the associated radioactive material storage facilities are closed or converted to other uses, the plant, equipment, site, and surrounding areas contaminated by radioactive shall be dealt with The environment shall be treated and radiation monitoring shall be carried out to ensure that relevant requirements are met after treatment. 8.2 After the associated solid radioactive waste landfill facility is closed, the site shall be closed for treatment and a permanent mark shall be set.

9 Guardianship

9.1 After the associated solid radioactive waste landfill facility is closed, the safety and stability of the facility and the effectiveness of radiation protection shall be monitored and monitored. The period is 30 years. 9.2 During the monitoring period, regular inspections should be conducted to maintain relevant facilities to prevent unrelated persons from entering, and regular radiation monitoring should be carried out. 10 Radiation monitoring 10.1 Requirements for radiation monitoring of associated radioactive material storage facilities 10.1.1 During the operation of the storage facility, an effluent monitoring plan should be developed in accordance with relevant requirements and combined with environmental impact assessment documents, and effluent monitoring should be carried out. 10.1.2 The materials should be monitored according to their source and batch. The monitoring items include 238U, 226Ra, 232Th, etc. 10.1.3 The radiation environment monitoring of storage facilities includes radiation background survey before operation, radiation environment monitoring during operation, and radiation environment monitoring after shutdown. 10.1.4 During the operation of storage facilities, a radiation environment monitoring plan shall be formulated in accordance with relevant requirements and combined with environmental impact assessment documents, and radiation Radiation environment monitoring work; the radiation environment monitoring plan at other stages can refer to the radiation environment monitoring plan during the operation period and adjust appropriately according to the actual situation. 10.2 Radiation monitoring requirements for landfill facilities of associated radioactive solid waste 10.2.1 The effluent monitoring requirements of landfill facilities are the same as 10.1.1, the solid waste monitoring requirements are the same as 10.1.2, and the radiation environment monitoring requirements are the same as 10.1.3 and 10.1.4. 10.2.2 The monitoring items during the monitoring period after the landfill facility is closed include. the radon release rate on the surface of the facility, the γ radiation air absorbed dose rate, and the liquid outflow The monitoring frequency of physical and groundwater monitoring well water U natural, 226Ra, Th, total α, total β, etc.; the monitoring frequency is 1 time/year, and it can be adjusted according to actual conditions after 2 years. When reducing the frequency of monitoring.

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