GB 15848-1995 Regulations on geological radiation protection and environmental protection of uranium mines
Some standard content:
National Standard of the People's Republic of China
Regulations for radiation and environment protection in uranium geology1 Subject content and scope of application
GB 15848--1995
This standard specifies the principles, dose limit standards, protection requirements and management measures for radiation protection and environmental protection in uranium geology. This standard is applicable to the production, scientific research and education departments of uranium geology, and can also be used as a reference by other geological departments engaged in natural radioactive materials.
2 Referenced standards
GB4792 Basic standards for radiation health protection
GB8703 Regulations on radiation protection
GB9133 Classification standards for radioactive waste
GB11215 General provisions for nuclear radiation environmental quality assessmentGB11806 Regulations for the safe transportation of radioactive materials3 Terminology
3.1 Radiation workers in uranium geology: workers whose occupations are accompanied by radiation exposure in uranium geology work. 3.2 Uranium mine exploration: underground operations conducted by uranium geological units to explore uranium geological resources. 3.3 By-product ore: uranium ore with a uranium content of more than one ten-thousandth produced during uranium mine exploration. 3.4 Uranium geological slag: a general term for by-product ores and other solid wastes produced during uranium geological exploration and other production processes. 3.5 Hydrogen evolution rate: the amount of hydrogen released from a unit area interface per unit time interval, in Bq/m2·s. 3.6 Equilibrium equivalent concentration (ECR): when hydrogen and any activity of its radioactive unbalanced hydrogen daughter mixture coexist in the air, for the convenience of protective monitoring, a quantity is used to measure the concentration of hydrogen instead of measuring the alpha potential concentration of the daughter mixture. The ECR of a radioactive unbalanced hydrogen daughter mixture in the air is the hydrogen concentration when it is in radioactive equilibrium with its hydrogen daughter mixture, at which time the two hydrogen daughter mixtures have the same total alpha potential concentration. The unit is J/m or Bq/m. 3.7 Balance factor (F) of alpha potential: the ratio of the equilibrium equivalent chlorine concentration (ECRa) to the actual radioactive concentration of hydrogen in the air (Crn): ECRn
(1)
3.8 Hydrogen daughters: short-lived decay products of hydrogen-222. Including -218 (RaA), lead-214 (RaB), bismuth-214 (RaC) and exo-214 (RaC').
3.9 Exposure to nitrogen daughters: the time integral of the concentration of chlorine daughters in the air. The units of exposure are different depending on the units used for the concentration of hydrogen daughters. When the concentration of hydrogen daughters is in Bq/m2 or J/m2, the exposure is expressed in Bg·h/m or J·h/m2, respectively. 3.10 Hydrogen daughters: short-lived decay products of hydrogen-220. Including -216 (ThA), lead -212 (ThB), bismuth -212 (ThC) and -212 (ThC').
3.11 α potential: In the nitrogen or hydrogen decay chain, the α potential of an atom is the total α energy emitted by the atom in the process of decaying to lead -210 (RaD) or lead -208 according to the decay chain. The unit is J. GB15848-1995
3.12 Alpha potential concentration in air: The sum of the α potentials of all hydrogen or short-lived decay product atoms of hydrogen in a unit volume of air! The unit is /m2.
3.13 Concentration of long-life α radiators in air: The sum of long-life α radiators contained in a unit volume of air, the unit is Bq/m. It is usually obtained by analyzing the total α concentration in a unit volume after the short-lived hydrogen daughters have decayed. 3.14 Working level (WL): A unit often used in uranium mines and geology to indicate the α potential concentration of hydrogen daughters. When the total α potential of hydrogen daughters or hydrogen daughters (regardless of the composition of various short-lived daughters) in 1L of air is 1.3×105Mev, its α potential concentration is called 1WL. When expressed in SI units, 1WL is equivalent to 2.08×10-5J/m4 General provisions
4.1 Radiation protection must comply with the three principles of "justification of practice, optimization of radiation protection, and maximum limit of personal dose"; environmental protection must implement the environmental laws and regulations and standards promulgated by the state, and adhere to the principle of "whoever pollutes, whoever governs". 4.2 Radiation protection and "three wastes" treatment facilities for new, expanded, and renovated projects must be designed, constructed, put into production, and accepted at the same time as the main project.
4.3 Uranium Geology Research Institute, uranium ore processing room and machine-dug tunnels with a main tunnel length of more than 500m shall submit an "Environmental Impact Assessment Report" in accordance with relevant regulations before construction and expansion. 4.4 All units engaged in uranium geological radiation work shall establish a protection organization or assign full-time (part-time) protection technicians to be responsible for radiation protection work, and report radiation protection monitoring data in accordance with relevant regulations. 4.5 Uranium geological radiation workers should strengthen safety and radiation protection knowledge education, and conduct regular assessments to make them consciously abide by various systems and regulations on radiation protection. New employees must undergo training and assessment by the radiation protection department and can only engage in radiation work after passing the assessment.
4.6 Uranium geological radiation work units should formulate management measures for radiation protection and environmental protection, radiation monitoring and its quality assurance outline and job responsibility system for their units in accordance with the requirements of these regulations and in combination with the specific conditions of their units. 5 Dose limits
5.1 The annual dose equivalent limits for radiation exposure to controlled sources and practices for uranium geological radiation workers and the public are shown in GB 8703.
5.2 Pregnant women, lactating women and persons under the age of 18 (including students and apprentices who need to be exposed) cannot engage in underground mining geological operations and must not receive special exposures planned in advance. Women of childbearing age who engage in radiation work should control their doses on a monthly basis. In addition to controlling the dose rate at an average monthly rate, the annual effective dose equivalent of pregnant women should be limited to less than 15 mSv. 5.3 The intake limits of common nuclides in uranium geology are shown in Appendix A (Supplement), and the annual intake limits (ALI) of other nuclides are shown in GB8703.
5.4 For workplaces where the short-lived daughters of hydrogen-222 and -220 are the main hazards, the annual intake limits of their short-lived daughters alpha potential are 0.02 J and 0.06 J respectively.
5.5 When radiation workers are exposed to both external radiation and internal radiation from multiple radionuclides, the annual dose equivalent limits of formula (2) and the relevant organs or tissues should be met at the same time.
(He)+≥
（ALI)z
Wherein: (He)out - annual effective dose equivalent produced by external exposure, mSv; Iz - annual intake of radionuclide i, Bq/a; (ALI)z~ - annual intake limit of radionuclide i, Bq/a; (2)
In underground uranium exploration workplaces, if the dose contribution of uranium-based long-lived radionuclides can be ignored, equation (2) can be simplified to equation (3):
GB15848-1995
(He)out+(He)→≤50
Wherein: (He)daughter - annual effective dose equivalent produced by daughter bodies to workers, mSv; other symbols are the same as in equation (2).
（3）
5.6When the underground daughter alpha potential concentration exceeds 4.16×10-J/m (2WL), in principle, the site should stop working. When the concentration is (2.08～4.16)×10-5J/m (1～2WL), effective protective measures should be taken. 5.7The effective dose equivalent received by radiation workers due to pre-planned special exposure shall not exceed 100mSv (10rem) in one event and 250mSv (25rem) in a lifetime and shall be subject to the annual dose equivalent limit of organs or tissues. Pre-planned special exposure must be approved by the unit or the superior radiation protection department and be carefully planned. 6Derived concentration of radionuclides
6.1For details of the air derived concentration and derived human consumption concentration of common nuclides in uranium geology, please refer to Appendix A (Supplement). For the air derived concentration of other nuclides, please refer to GB8703.
6.2 The derived concentration is only a reference value given for the convenience of design, management and monitoring. On the basis of not exceeding the annual intake limit, the derived concentration can be increased or decreased according to the actual intake situation. 6.3 When only exposed to nitrogen-222 and hydrogen-220 gas itself without its daughter mixture, or when the amount of its short-lived daughter inhaled is extremely small and can be ignored (such as wearing a mask made of high-efficiency filter material), the air derived concentration of nitrogen-222 and hydrogen-220 can increase by 100 times. 7 Control level of radioactive surface contamination
7.1 The control level of radioactive surface contamination shall be implemented in accordance with GB8703. 7.2. The pollution level of indoor walls, equipment and ground adjacent to the radiation workplace shall not exceed one-tenth of the workplace surface pollution control level.
8 Main protection requirements for the workplace
8.1 The classification of radiation workplaces and the classification of open radioactive workplaces refer to GB4792. 8.2 Class A open radiation workplaces shall not be located in urban areas. When necessary, they must be reviewed and approved by the radiation protection and environmental protection departments.
8.3 Newly built radiation workplaces should be located in locations with low population density and good dilution and diffusion conditions for radioactive waste gas, and should be concentrated in one area as much as possible, and arranged on the upwind side of residential areas or other workplaces according to the local minimum frequency wind direction. 8.4 For new workplaces, at least three candidate sites should be selected, comprehensively evaluated, and selected based on merit. 8.5 There should be a certain protective distance between the radiation workplace and residential areas and drinking water sources, as shown in Table 1. The area within this distance is designated as a planning restricted area. Radioactive materials in this area should be monitored regularly. 8.6 In any workplace where radioactive dust or aerosol is generated, the floor, walls and ceiling should be decorated with building materials that are not easily contaminated and should be smooth; the interior structure should be simple, reduce dust accumulation and be easy to clean. Mineral analysis rooms and sample crushing rooms should have cement floors and be equipped with floor drains and sewage treatment pools. Acid-resistant and alkali-resistant workbenches should be installed in any workplace with strong acids or alkalis. 8.7 Uranium ore samples must not be piled in places where people frequently enter and exit. 8.8 The height of the exhaust gas discharge pipes in the uranium ore processing room and the smelting room must exceed the highest roof ridge in the surrounding area (within 50m). Table 1 Planning limit distance of radioactive workplaces in uranium mines Radioactive work
Other places
Residential area
Drinking water source
Ore specimens and
Model display room
Crushing room
Melting room
Ore processing room
Tunnel exhaust vent, waste slag
Storage yard, hydrometallurgical workshop
9 Dust prevention and oxygen reduction
GB15848-1995
9.1 In the workplace, comprehensive measures such as "strengthening ventilation, insisting on wet operation, sealing hydrogen dust source, doing a good job of personal protection, strengthening the management of protective facilities and regular inspections" must be taken to reduce the concentration of harmful substances in the air to below the national standard. 9.2 All ground workplaces that produce radioactive dust and harmful gases must have ventilation devices. The ventilation system should prevent the backflow of pollutants. The dust concentration at the air inlet should not be greater than 0.1mg/m2, and the chlorine concentration should not be greater than 150Bq/m. 9.3 Requirements for ventilation:
9.3.1 Mechanical ventilation should be used for horizontal tunnels and inclined shafts with a depth of more than 20m, vertical shafts or shallow shafts with a depth of more than 10m, and skylights with a depth of more than 5m. The working face should adopt pressure ventilation, and the end of the pressure air cylinder should not be more than 10m away from the working face. When the depth of the branch tunnel or tunnel turns and excavates more than 5m, there should be special ventilation.
9.3.2 When working in the tunnel, ventilation must be carried out first to reduce the equilibrium equivalent hydrogen concentration in the pit to about 2.08×10-5J/m, and the ventilation time must not be less than 15min. The ventilation must not be stopped when there are people in the pit. 9.3.3 The ventilation volume should first be determined to meet the air volume required to reduce the hydrogen and its daughters in the tunnel to below the limit concentration. 9.3.4 The exhaust air outlet of the tunnel should be located on the upwind side of the minimum wind frequency of the air inlet, and the air outlet should be at a certain distance from the air inlet, so that the dust concentration at the main air inlet of the tunnel is not more than 0.1mg/m2, and the hydrogen concentration is not more than 150Bg/m; the dust concentration at the working face is not more than 2mg/m. 9.4 Underground sealing and hydrogen reduction measures:
9.4.1 Completed tunnels should be closed in time. The closure should be tight and firm. If you need to enter a closed tunnel for work, you must obtain the consent of the protection department, wear a gas respirator and a personal dosimeter, and reseal it immediately afterwards. 9.4.2 The ore-seeking and fracture-developed sections of the main tunnel should be sprayed with a hydrogen-proof covering layer to reduce hydrogen precipitation. And minimize the retention time of ore in unclosed tunnels.
9.4.3 The tunnel drainage ditch should be cleaned regularly to keep the water flowing smoothly. For underground water with high hydrogen concentration, a special pipe should be installed to discharge the water directly to the wastewater treatment facilities outside the pit.
9.4.4 The tunnel along the vein must be designed outside the vein. During construction, by-product ore and waste rock must be piled separately. 10 Discharge and treatment of uranium geological wastes
10.1 Uranium geological waste residue with radioactive specific activity greater than 7.4×10*Bq/kg should be backfilled as much as possible. Waste residue rock with specific activity less than 7.4×10°Bq/kg should be stored stably by building a dam or shallowly treated on the spot, and then covered with loess vegetation; the treatment site should be selected in a place far away from residential areas and water sources, not easily washed away by rainwater and where the groundwater system is not developed. 10.2 When using heap leaching to treat by-product ore, measures should be taken to prevent secondary pollution to the environment, and the waste residue produced by heap leaching should be treated according to 10.1.
10.3 Combustible pollutants such as labor protection products, paper, and wood that cannot be recycled should be incinerated in places that meet protection requirements, and the remaining ash should be buried together with other solid wastes.
10.4 Waste liquid from the mine analysis room should be poured into a special waste liquid pool, treated regularly, and any discharge is prohibited. A special tailings pool must be set up in the sample crushing room and treated regularly.
10.5 Wastewater discharged during the drilling process must be treated in a sedimentation tank and must not be directly discharged into farmland or economic waters. After the drilling is completed, proper and reliable sealing measures must be taken. 10.6 When wastewater is discharged into rivers, the wastewater discharge volume and discharge concentration should be controlled according to the dilution capacity of the river to ensure that under the most unfavorable conditions, the radioactive nuclide concentration at the nearest water intake point downstream of the discharge port is not greater than the derived ingestion concentration. 10.7 The additional concentration of airborne radionuclides in the public living environment caused by waste gas emissions shall not exceed 0.6 times the DAC public on average per year. When the exhaust gas emission makes the annual intake of key population groups greater than 1/3 of the corresponding annual intake of the public, in addition to limiting the emission concentration, the total emission must also be limited.
10.8 The emission and treatment of non-radioactive nuclides shall refer to the relevant national regulations. 206
11 Decommissioning of radiation workplaces
GB15848—1995
11.1 If the content of radioactive nuclides in the water discharged from the completed tunnel exceeds the prescribed standard, a water blocking wall shall be built at the tunnel entrance. 11.2 The radiation workplace must be treated before being abandoned. After treatment, the waste slag stone dump site shall be marked with solid and obvious signs to prevent damage. The surface hydrogen evolution rate shall not be greater than 0.74Bq/m2·s. 11.3 When the radiation workplace is decommissioned, comprehensive monitoring shall be carried out and a radiation environment quality assessment shall be made. 11.4 Radioactive waste residues shall not be used as building materials, and people shall not live on radioactive waste residue dump sites. 12 Management of Radioactive Standard Sources and Transportation of Radioactive Materials 12.1 Sealed radioactive sources with a radioactivity greater than 5×104Bq must be uniformly registered and managed by the geological unit’s user department, and a designated person must be designated to keep them. The procedures for receiving and handing over must be strictly followed, and they must be regularly inspected, counted, and verified. The ordering, allocation, and scrapping of radioactive sources must be reported to the security department for record. Scrapped radioactive sources must be handled in accordance with relevant regulations. 12.2 Solid radium sources must be placed in lead cans and placed together in a locked, secure container. The dose equivalent rate at any point 5 cm from the container surface must not exceed 2.5uSv/h, and they must be placed in a safe and reliable source library. 12.3 Radiation sources must be regularly checked for leaks. 12.4 When transporting solid radium sources, the sources must be placed in containers that meet protection requirements, and it is strictly forbidden to carry them on public transportation. 12.5 If a radium source is lost or damaged, immediate measures must be taken to prevent the accident from expanding and to avoid contamination of the body and wounds. And report to the competent and supervisory departments in a timely manner. For the classification of radioactive source loss accidents and the format of the accident report form, please refer to GB8703. 12.6 When using a radium standard source, the contact time must be shortened as much as possible, the operating distance must be expanded, and shielding measures must be taken. 12.7 When transporting ores and ore samples, measures must be taken to prevent leakage and dust. Vehicles carrying ore must be carefully cleaned and decontaminated after use. 12.8 Railway transportation shall be carried out in accordance with GB11806.
13 Personal protection and sanitary facilities
13.1 Showers, changing rooms and health boxes must be set up in radioactive dust workplaces such as tunnel entrances and sample crushing rooms in uranium mine exploration. 13.2 Protective equipment must be worn when entering the radiation workplace; eating, drinking, smoking and storing food are prohibited in the radiation workplace; radiation workers must wash their hands and rinse their mouths before eating. The protective equipment used should be cleaned frequently and must not be brought back to the living area. 13.3 If injured during radiation work, the area around the wound should be decontaminated with medical disinfectant in a timely manner and a doctor should be consulted. 14 Medical Supervision
14.1 All personnel engaged in uranium geological radiation work must undergo a health examination in accordance with the requirements of 10.1.3 of GB8703 before employment. Those who do not meet the "basic health" requirements shall not be engaged in this work. The health standards for radiation workers are shown in Appendix K of GB8703. 14.2 Uranium mine geological radiation workers should be subject to medical supervision. Those whose exposure dose equivalent is close to or may exceed the annual dose equivalent limit shall undergo a physical examination once a year (dust workers shall also take a chest X-ray); those whose exposure dose equivalent is less than three tenths of the annual dose equivalent limit shall undergo a physical examination every two to three years; for those exposed in radiation source accidents, if the intake of radionuclides exceeds twice the annual intake limit, a blood test and necessary treatment shall be carried out in a timely manner.
14.3 The diagnosis of occupational diseases such as silicosis shall be carried out by a specialized hospital for occupational diseases designated by the competent department. 14.4 Units engaged in uranium mine geological work shall have full-time (part-time) labor health doctors responsible for occupational health management and establish health records for radiation workers. The health records shall be kept for no less than 30 years after the cessation of such work. 14.5 Personnel who are not suitable for uranium mine geological radiation work must change their jobs in a timely manner. 14.6 Before the dust prevention measures are completely resolved, in addition to actively taking protective measures, the cumulative working time of groove sampling workers shall not exceed 2 years. 14.7 The medical treatment of radiation workers who are exposed to abnormal radiation shall be handled in accordance with the provisions of 10.2.3 to 10.2.5 of GB8703. 15 Monitoring
15.1 Personal dose monitoring:
GB15848--1995
15.1.1 Radiation workers who work underground in uranium mines, crush ore, make high-grade ore models, and whose annual intake may exceed three-tenths of the annual dose limit shall undergo personal internal radiation dose monitoring and skin and clothing contamination monitoring. 15.1.2 Personnel engaged in calibration and leak detection of radium standard sources, personnel engaged in pit exploration in areas with a bell ore grade greater than 0.5%, and other radiation workers whose annual external radiation dose may exceed three-tenths of the annual dose limit must undergo external radiation personal dose monitoring. 15.1.3 Personnel exposed to radiation source accidents and other abnormalities shall undergo timely personal dose tracking monitoring. 15.1.4 For personnel whose personal internal and external radiation dose is greater than one-tenth of the annual limit, but is unlikely to exceed three-tenths of the annual dose limit, it can be estimated through routine monitoring of hydrogen, ammonia and γ external radiation in the workplace and investigation of working hours. If necessary, personal dose monitoring of nitrogen and radiation can be carried out on some representative workers. 15.1.5 When the annual internal and external radiation dose of radiation workers is equal to or higher than three-tenths of the annual dose limit, the reasons should be found out and corresponding radiation protection evaluation should be made.
15.1.6 When radiation workers are transferred, their personal dose file data should be transferred to the radiation health department of the new unit. Personal dose files should be kept until 30 years after the radiation workers leave radiation work. 15.1.7 When radiation workers diagnose radiation damage, they must have personal dose monitoring data as a basis. 15.2 Workplace monitoring:
Routine monitoring should be carried out in all radiation workplaces. 15.2.1
15.2.2 Monitoring items in the workplace should include: a.
Alpha potential concentration of chlorine and ammonia progeny in the air, dust concentration and concentration of long-life alpha radiators in the air. Radiation level.
Content of uranium, radium, needle and total alpha in the discharged wastewater. Detection of the effectiveness of ventilation system, "three wastes" treatment system and related protective facilities. The monitoring cycle of various types of radioactive workplaces is shown in Table 2. 15.2.3
Table 2 Monitoring cycle of various types of radiation workplaces Workplace
Monitoring items
Hydrogen, hydrogen progeny
Y, X-ray external irradiation
Long-life alpha in the air
Radiator concentration
Wind speed, air volume
15.3 Radiation environment monitoring:
Machine-dug tunnels
Hand-dug tunnels
15.3.1 Radiation Background survey before starting work in the workplace Sample crushing room
Analysis room
X-ray radiation
Radiation site
Radium standard
Ore model
Production roombzxz.net
Times/month
Reverse sample 1/6
15.3.1.1 For machine-driven tunnels with a main tunnel excavation volume of more than 500m, water metallurgical workshops, medium-sized and above uranium deposits, mineral sample crushing rooms, processing rooms and analysis rooms above Grade C, a background survey should be carried out before construction. 15.3.1.2 Scope of background survey: The monitoring radius of machine-dug tunnels, water-metallurgical plants and medium-sized or larger ore deposits is 3000m, and that of other radioactive workplaces is 1000m. With the pollution source as the center, concentric circles with radii of 500, 1000, 2000, 3000m or 50, 100, 500, 1000m are drawn in the monitoring area, and 64 sub-areas are divided according to 16 directions. The sub-areas where residents live and have close relations with residents and the sub-areas on the leeward side of the dominant wind direction are investigated in particular. The river should be investigated along its flow direction until the background is monitored. If the impact is large, the scope of investigation should be expanded. 208
GB15848--1995
15.3.1.3 Survey objects: surface water, atmosphere, bottom sediment, soil and edible organisms. 15.3.1.4 Investigate radionuclides: hydrogen and its daughters in the atmosphere, natural uranium, radium-226, natural needles, hydrogen precipitation rate, natural uranium, radium-226, natural needles, total alpha in water and edible organisms, and further analyze Pb-210 and Po-210 when the total alpha in the sample is high. 15.3.1.5 Investigation time: once in the flood season and once in the dry season. 15.3.2 Routine environmental monitoring in normal production The monitoring items, frequency, radionuclides and locations are shown in Table 3. The monitoring scope is the same as 15.3.1.2. 15.4 In the event of a loss of radium or other radioactive sources, dose tracking monitoring must be carried out on the exposed personnel. When contaminated by broken radium sources, alpha and beta surface contamination monitoring must be carried out on the victim's clothes and exposed human surfaces. Units with conditions must conduct internal irradiation monitoring. Table 3 Routine items, frequency, nuclides and location items of radiation environment
Waste slag stone
Other water bodies
Sampling frequency
Times/year
15.5 Monitoring and analysis methods and quality assurance: 15.5.1
, daughters, total α
Hydrogen, hydrogen daughters, total α
Monitoring nuclides
Specific activity, re-precipitation rate, Y irradiation dose rate Natural uranium, needle, radium-226, outer-210, lead-210 Natural forceps, needle, radium-226, needle-210, lead-210 Natural uranium 、Ra-226、Total α
Natural uranium, radon, radium-226
Natural uranium, radon, radium-226
Sampling location
Emission outlet
Downwind of the dominant wind
Degree slag dump
Emission outlet
Downstream of the emission outlet
Wastewater flow area
Wastewater flow area
Downstream of the emission outlet
Monitoring and analysis methods shall be carried out in accordance with relevant national standards. The dust, hydrogen, daughter body and external irradiation monitoring methods are as follows: Dust concentration is measured by filter membrane weight method. Chlorine concentration adopts scintillation chamber method, balloon method or ionization chamber method. The cumulative determination of hydrogen concentration can be carried out by track etching method. The hydrogen daughter α potential concentration adopts Markov method or Kuznets method. For individual external irradiation, thermoluminescent dosimeter is used.
15.5.2 Monitoring quality assurance must be carried out throughout the development of monitoring plans, sample collection, storage, transportation, analysis and evaluation of monitoring results. For specific quality assurance measures, please refer to relevant regulations. 15.6 The radiation protection evaluation and radiation environment quality evaluation of radiation workplaces shall be carried out in accordance with relevant standards such as GB8703 and GB11215. 15.7 The results of personal dose monitoring and radiation monitoring shall be reported to the competent and supervisory departments in the form of Appendix B (Supplement) and filed. 209
Pb-210
Po-210
Rn-220
Rn-222
Equilibrium equivalent oxygen
concentration (ECRn)
Ra-226
Th-230
Natural needle and
Th-232
Natural uranium and
U-238 long-lived
Life-alpha mixture
Th-232 long-lived
Life-alpha mixture
GB15848-1995
Appendix A
Annual number of common radionuclides in uranium geology ALI and derived air concentration (DAC), derived ingestion concentration (DIC) (supplement)
Radiation workers
ALI,Bg
2×104
1×105
3×10*
4×105
5×10s
5×105
9×10°
2×104
2×104
6×102
1×102
1×103
2×109
2×103
Public ALI,Bq
4×102
2×103
2×103
8×103
1×10*
1×10*
1.2×10-3J
4×10-\J
Note: ① Uranium is introduced by the ALI of its oxides and hydroxides. ② Uranium is introduced by the ALI of its water-soluble inorganic compounds and the ALI of its oxides. ③For the calculation methods of the public derived air concentration and derived ingestion concentration, please refer to GB9133.210
Radiation work
place air derived concentration
2.5×10-5
(J/m')
(J/m2)）
2×10-2
4×10-1
6×10-2
6×10-1
7×10-1
7×10-1
Public air derived concentration Degree
1.7×10-2
3.8×10-2
1.1×10-7
(I/m2)
3.8×10-8
(J/m°)
3.8×10-2|| tt||1.1×10~3
1.9×10-4
1.9×10-3
3.8×10-3
3.8×10-3
3.2×10-3
7.2×10-4| |tt||Derived ingestion concentration
5.0×10-1
Species name
Unit name:
Number of people on the side
GB15848---1995
Appendix B
Comprehensive annual report of radiation monitoring data
(Supplement)
Table B1 Annual report of personal dose of radiation workers Rat body dose Radiation exposure dose,
α aerosol dose,
Unit head:
Security department head:
Reporting date ：
Fill in the form:
Annual total dose,
Collective dose,
person·mSv
GB15848—1995
Total number of samples (pieces)
Huahai Guozhongdao
Total number of samples (pieces)
·Yahua
Total number of samples (pieces)
Neng Guozhongcheng
Total number of samples (pieces)
GB15848-1995
Additional notes:
This standard was proposed by China National Nuclear Corporation. This standard was drafted by the Nuclear Industry Geological Bureau. GB158481995
The main drafters of this standard are Lin Qingquan, Song Lanying, Zhang Zhiku, Zhang Hong, and Lao Jieyu. ：214
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