GB 17568-1998 Specification for the design, construction and use of gamma irradiation equipment
Some standard content:
GB17568—1998
This standard is compiled with reference to the International Atomic Energy Agency (IAEA) No. 107 Safety Series "Radiation Safety of X-ray and Electron Beam Irradiators" (1992 Edition), the United States Code of Federal Regulations (CFR) Title 10 Part 36 "Licensing and Radiation Safety Requirements for Large Irradiators" (10CFRCh.197 Edition), the American National Standard N.43.10 "Safety Design and Use of Fixed Source Chamber Wet Source Storage X-ray Irradiators (NV)", N43.7 "Safety Design and Use of Self-shielded X-ray Irradiators (I)", etc. Appendix A of this standard is the standard appendix.
Appendix B of this standard is the reminder appendix. This standard was jointly proposed by the Radiation Processing Professional Committee of the China Isotope and Radiation Industry Association and the Science and Technology Bureau of China National Nuclear Corporation. This standard is under the jurisdiction of the China Nuclear Industry Standardization Institute. Drafting units of this standard: The Second Research and Design Institute of Nuclear Industry is responsible for drafting, and the Nuclear Industry Standardization Institute and the Radiation Processing Professional Committee of the China Isotope and Radiation Industry Association participated in the drafting. The main drafters of this standard are: Wang Chuanzhen, Tang Zaimin, Zhang Hehu, Ren Lun, Jiang Shiming, Han Quansheng, Hou Fuzhen. 331
1 Scope
National Standard of the People's Republic of China
Regulations for design construction and use of gamma irradiation facilities
Regulations for design construction and use of gamma irradiation facilities This standard specifies the technical requirements and management regulations for the design, construction and use of irradiation facilities. This standard is applicable to irradiation facilities with cobalt-60 source, chalcanthite-137 source and other radioactive sources. 2 Referenced standards
GB 17568--- 1998
The provisions contained in the following standards constitute the provisions of the standards through reference in this standard. When this standard is published, the versions shown are valid. All standards will be revised, and parties using this standard should explore the possibility of using the latest versions of the following standards. GB3/T1804--1992 General tolerances Unspecified tolerances for linear dimensions G33095-1996 Ambient air quality standard G3 4075-1983
Classification of sealed radioactive sources
GB 4076 -- 1983
General provisions for sealed radioactive sources
GB 4792---1984
GB 7465-1994
GB 8703-1988
Basic standards for radiation health protection
High activity cobalt-60 sealed radioactive sources
Radiation protection provisions
GB 10252-1996
GB 11806-1989
Radiation protection and safety standard for Drill-60 irradiation device Regulations for safe transportation of radioactive materials
GB/T15446-1995 Terminology of radiation processing dosimetry JJG591---1989 Verification procedure for radiation sources (for radiation processing) TJ36--1979 Hygiene standard for design of industrial enterprises [Order No. 44 of the Ministry of Transport of China] Regulations on Radiation Protection of Radioactive Isotopes and Radiation Devices 3 Definitions
This standard adopts the following definitions.
3.1 Ionizing radiation Ionizing radiation is radiation composed of charged particles and (or uncharged particles) that can produce ionization. Ionizing radiation is also called rays. 3.2 Radiation source radiation source
A device or substance that can emit ionizing radiation. 3.3 Radioactive source Any amount of radioactive material used as a source of ionizing radiation. 3.4 Radiation field radiation field
The spatial-temporal distribution of ionizing radiation in the medium under consideration. Approved by the State Administration of Quality and Technical Supervision on November 17, 1998 332
Implemented on July 1, 1999
3.5 Radiation processing radiation processing GB 17568--1998
Improvement of the quality or performance of a substance by the action of ionizing radiation (rays). 3.6 Gamma irradiation device gamma irradiation Facilities are devices that use gamma radiation (rays) to process items and materials through safe and reliable radiation processing technology: its classification is shown in Appendix B (suggestive appendix), and its components are shown in Appendix A (standard appendix). 3.7 Processing capability processing capability The maximum value of the product of the amount of material and the absorbed dose that the irradiation device can process per unit time. 3.8 Absorbed dose absorbeddose
The quotient of the average energy de given by ionizing radiation to a substance with a mass of dm divided by the mass of the substance dm. The unit of absorbed dose is gray, and the symbol is Gy, lGy=1 J/kg.
3.9 Dose measurement system dosimetrysystem A system for measuring dose composed of dosimeters, related analytical instruments and dose response calibration curves or dose response functions. 3.10 Dose ununiformity dose ununiformity The ratio of the maximum to the minimum absorbed dose in the same batch of products, that is, U=Dmax/Dmin. 3.11 High Radiation Area For irradiation equipment, all areas where personnel may be exposed to dose rates exceeding 1mSv/h should be considered high-radiation areas. For example, irradiation rooms and mazes.
3.12 Control area
All high-radiation areas are control areas. For irradiation equipment, the area within the entrance of the maze of the irradiation room is a control area. 3.13 Supervision area The operation area, control room, ventilation room, equipment room, source room, water treatment room and the areas with a limit of 1/10~3/10 of the annual effective dose equivalent are all supervision areas.
3.14 Non-restricted area non-control The working area with a limit value not exceeding 1/10 of the annual effective dose equivalent is a non-restricted area. 4 General Provisions
4.1 Safety Provisions for Devices
4.1.1 During the design, construction, installation, commissioning, operation and maintenance of irradiation devices, health and safety evaluation must be carried out in accordance with the State Council Order (1989) No. 44 and the regulations of relevant departments and this standard. 4.1.2 The standards for health and safety evaluation of irradiation devices shall be in accordance with the provisions of this standard and the provisions of GB10252-1996, GB4792--1984 and GB8703-1988.
4.1.3 The design, construction, installation, commissioning and management of irradiation devices must comply with the following safety principles. 4.1.3.1 Defense in Depth Principle
Defense in depth is a multi-level defense, which is to reduce human intervention factors to the minimum level so that necessary corrections or compensation can be obtained in the event of a failure or accident.
a) The purpose of the first level of defense is to prevent deviations from normal operating conditions. For example: T. Necessary interlocks between sequences, formulate and implement corresponding quality assurance plans at each stage;
b) The purpose of the second level of defense is to detect and control deviations from normal operating conditions to prevent expected operating events from escalating into accident conditions. The requirement at this level is to set up special systems and formulate operating procedures to prevent these hypothetical initiating events or mitigate their hazards; c) The purpose of the third level of defense is to mitigate the consequences of accidents, especially by achieving stable and acceptable operating conditions. This requires the establishment of necessary additional equipment and procedures; d) The irradiation device can only operate under the condition that all levels of defense measures are in place and can function normally. 4.1.3.2 Redundancy
GB 17568--1998
Redundancy uses more items than the minimum number of items required to complete a certain safety function, so that the whole will not lose its function if a certain item fails or does not work during operation. For example, there should be 2 interlocks in general, and 3 to 4 in important places.
4.1.3.3 Diversity
Diversity can improve the safety and reliability of the device, including system diversity and multiple dose monitoring can use different operating principles, different physical variables, different operating conditions, different components, etc. For example: the safety interlock of personnel access can use mechanical, electrical, dose, and electronic interlocks.
4.1.3.4 Independence
Independence means that when a safety component fails, it will not cause other safety components to fail or lose their functions. The safety mechanism is made independent by means of functional separation and physical isolation. To improve the independence of the system, the following measures can be taken: a) Ensure the independence between redundant (multi-channel interlocking) components; b) Ensure the independence between multi-level defense components; c) Ensure the independence between multiple components. 4.1.4 Safety signs
Radioactive symbols and warning signs should be set at the entrance of the irradiation device plant and other necessary places. The radioactive symbol is shown in Figure 1:
4.1.5 Radioactive material contamination limit
For water well storage irradiation devices, the concentration of radioactive contaminants such as D-60 contained in the water of the storage well should be controlled below 10Bq/L. The surface contamination of β radioactive substances on the clothes, body surface of the staff and the equipment, tools, ground and other surfaces in the workplace should be controlled within the level specified in 3.3.3 of GB10252-*-1996.
4.2 Radiation Protection Guidelines
4.2.1 Radiation Protection Design Management Regulations
The design, construction, inspection and acceptance of radiation protection for irradiation devices must be undertaken by units and personnel with corresponding qualifications. Management during operation shall be carried out in accordance with Order No. 44 of the State Council and the relevant regulations of the relevant competent authorities. 4.2.2 Optimization of Radiation Protection
The design and construction of irradiation devices require that all exposures be kept within the specified limits, and after considering social and economic factors, the principle of "as low as reasonably achievable" must be implemented to ensure that the exposure of radiation workers and the public reaches the "level as low as reasonably achievable", that is, the AI.ARA (As Low As Reasonably Achievable) principle. 4.2.3 Personal Dose Limits
Personal dose limits are part of the radiation protection system and are constraints in the optimization process. The following dose limits do not include natural background exposure and medical exposure:
a) The annual effective dose equivalent limit for radiation workers is 50 mSv; b) The annual effective dose equivalent limit for members of the public is 1 mSv. 334
1D size is determined according to the site:
2 Color package: the base color is orange, and the two-leaf shape is black. GB17568
—1998
However, the dose limit specified here is the lower limit of the unacceptable dose range, not the upper limit of the acceptable dose range, and it cannot be directly used for the purpose of design and work arrangement. In engineering design, the dose limit for radiation protection design is specified as follows: a) The annual effective dose equivalent limit for radiation workers is 5 mSv; b) The annual effective dose equivalent limit for members of the public is 0.1 mSv; c) When calculating shielding, take a safety factor of not less than twice. 4.2.4 Division of radiation workplaces
The irradiation device is divided into a controlled area (marked in red), a supervised area (marked in orange) and a non-restricted area (marked in green). Each area shall be subject to dose supervision.
4.3 Dose measurement regulations
4.3.1 The irradiation device shall be equipped with a corresponding dose measurement system in accordance with the requirements of Appendix A3 of this standard to monitor the radiation field and product dose and ensure the safety of personnel, equipment and environment. 4.3.2 Before the irradiation device is put into use, it must be calibrated by units and personnel with corresponding qualifications in accordance with the requirements of JIC591-1989 before it can be put into operation.
4.3.3 The irradiation device must pass the assessment and obtain the "Radiation Processing Measurement License" and be re-inspected in accordance with the regulations. 4.3.4 Before the irradiation device is installed and put into use, the shielding effect must be tested in accordance with the requirements of the partition limit. The measuring point position is stipulated as the effective center of the detector probe 30cm away from the surface of the shielding wall, and the average value is taken in the space with a nonlinear length greater than 20cm and an area not greater than 100cm.
4.4 Operation Management Regulations
4.4.1 After the irradiation device is completed, it must be inspected and accepted by units and personnel with corresponding qualifications in accordance with Order No. 44 of the State Council and the relevant regulations of the relevant competent authorities, and it can only be officially put into operation after obtaining a license registration certificate. 4.4.2 The operators of the irradiation device must undergo training and pass the examination in accordance with the provisions of 11.2, and obtain a job certificate before they can start working! 4.4.3 All operations should formulate operating procedures, safety procedures, maintenance procedures and a job responsibility system, and strictly implement them. 4.5 Quality Assurance Provisions
4.5.1 The owner, design, manufacturing, construction, installation, and operation management units of the irradiation device must obtain the corresponding qualification certificates and quality certifications in accordance with the provisions of this standard and relevant national laws and regulations. 4.5.2 The owner of the irradiation device must formulate a comprehensive quality assurance outline and outline procedures and work instructions for all activities such as site selection, design, manufacturing, construction, installation, operation management and decommissioning of the irradiation device, and ensure that they are implemented throughout the entire process. The design, manufacturing, construction, installation and operation units should formulate quality assurance outlines for their activities based on the owner's quality assurance outline and be responsible for their effectiveness.
4.5.3 In order to meet quality requirements, it is necessary to establish inspection points for key steps and parts, conduct effective monitoring, and keep records as the main basis for quality verification and traceability.
4.6 Responsibilities
4.6.1 Owner
The owner refers to the owner of the irradiation device and is fully responsible for the device. His responsibilities are: a) Complete various approval procedures, including approval procedures for the site, design, construction, acceptance and other contents; b) Select qualified design, manufacturing, construction, installation and source supply units; c) Provide training to the employed operators in accordance with the provisions of this standard and other relevant national standards, and apply for job qualification certificates; d) When the owner is the operating unit, it shall also bear the responsibilities of the operating unit in 4.6.6. 4.6.2: Design unit
refers to the unit that is qualified to undertake the design of irradiation device engineering and equipment. Its responsibilities are: a) Accept the entrustment of the owner, design the irradiation device engineering and equipment in accordance with the provisions of this standard and other relevant national standards, and provide relevant technical documents in accordance with relevant national laws and regulations; b) Accept the entrustment of the owner, provide technical services for engineering construction, equipment manufacturing, installation and commissioning; c) Participate in the completion acceptance of the project in accordance with relevant regulations. 4.6.3 Manufacturing unit
refers to the unit that is qualified and capable of undertaking the processing and manufacturing of the process equipment of the irradiation device. Its responsibilities are: a) to manufacture the process equipment of the irradiation device in accordance with the design drawings and relevant national standards and specifications; b) to formulate quality assurance measures during processing and manufacturing, implement them conscientiously, keep records, and form technical documents. 4.6.4 Construction unit
refers to the unit that is qualified to undertake the construction of the civil engineering and public engineering of the irradiation device. Its responsibilities are: a) to carry out the construction and installation of the civil engineering and public ancillary engineering of the irradiation device in accordance with the design drawings and relevant national standards and specifications; b) to keep records of the modified parts of the design drawings during construction for use as engineering evaluation during acceptance and other inspections; c) to accept inspection and acceptance.
4.6.5 Installation unit
refers to the unit that is qualified and capable of undertaking the installation and commissioning of the process equipment of the irradiation device (including loading the radioactive source). Its responsibilities are: a) to carry out the installation and commissioning of the process equipment of the irradiation device in accordance with the design drawings, technical documents provided by the manufacturing unit and relevant national standards and specifications;
b) to accept inspection and acceptance.
4.6.6 Operation unit
refers to the unit that is qualified and capable of undertaking the operation of the irradiation device. Its responsibility is to carry out the daily operation and management of the irradiation device in accordance with the provisions of this standard and other relevant national standards. 4.7 Quality system and environmental management system certification In order to ensure the quality of the irradiation device and ensure personal and environmental safety, the units engaged in the design, manufacture, construction, installation and operation management of the irradiation device for radiation processing must have a sound quality management system and environmental management system. It is recommended to apply for certification from the relevant statutory quality system and environmental management system certification bodies. The certification body must be accredited by the China National Accreditation Board for Quality System Certification Bodies (CNACR) and the China National Accreditation Board for Environmental Management System Certification Bodies. Its accredited business scope should cover the scope of application of this standard GB 17568-1998. And obtain the quality and environmental management system certification certificates for the relevant business scope. Wide site selection of 5Y irradiation device
5.1 Requirements for the site
a) The site of the irradiation device should avoid destructive earthquake activity areas as much as possible, as well as areas where the groundwater level is too high and the underground soil is too soft, causing the building to sink and tilt.
b) It is required to avoid high-voltage transmission corridors and flammable and explosive places; c) Irradiation devices designed and constructed in areas where there is a possibility (90% probability within 50 years) of severe destructive earthquakes (earthquakes with ground horizontal acceleration greater than or equal to 0.3g) should be equipped with earthquake detectors. Once the detector reacts, the radiation source can automatically enter a fully shielded state.
5.2 Requirements for the surrounding environment
The irradiation device should be built in a place with convenient transportation, where the roads and bridges can withstand 10-ton automobile transportation, and there are no special requirements for the surrounding environment. 5.3 Determination of the site
Combining the above requirements, collecting hydrological, geological, meteorological, demographic, and geographical environmental data, and evaluating the geology and environment, the superior competent department shall approve and determine the site.
6 Design of irradiation equipment
6.1 Qualifications of design units and their personnel
6.1.1 The design unit of the irradiation device shall hold the corresponding nuclear engineering design certificate or quality system certification in accordance with the requirements of this standard and other relevant national regulations. Copies or photocopies of these documents should be included in the design documents. 6.1.2 The designers responsible for the irradiation device should be familiar with nuclear engineering technical knowledge, and each type of work should have 1 to 2 senior engineers or engineers with nuclear engineering design experience to review the design. 6.2 Design principles
6.2.1 The design unit shall reasonably determine the engineering scale, source quantity and other ancillary facilities of the irradiation device based on the owner's commissioned task book. 6.2.2 The design unit shall design the irradiation device in accordance with the provisions of this standard and relevant national standards. 6.2.3 When undertaking the design of irradiation equipment, the design unit shall determine the specific composition of the irradiation equipment in accordance with this standard and relevant national regulations.
6.3 Design calculation
Ya The shielding protection, ventilation and important components of the irradiation equipment shall be calculated according to the appropriate and effective verified calculation methods in existing standards and publications. The calculation results shall be explained in the design documents. The calculation book shall be properly kept by the design unit for reference during re-calibration. 6.4 Design requirements
6.4.1 Interlocking requirements
Ya The irradiation equipment must be equipped with a fully functional and reliable safety interlocking system to effectively monitor and interlock the control area, especially the entrances and exits, source operating system, irradiated material transportation system, etc.: 6.4.2 Key control
The switches of the radioactive source elevator, the personnel passage door and the cargo passage door of the irradiation room must use independent multi-purpose keys or multiple keys together. This key or a bunch of keys must also be connected to an effective portable radiation detection alarm. The key must be used only by the duty supervisor or safety officer.
A small calibration source, such as a 0.37MBq cerium-137 source, should be installed at the personnel entrance of the irradiation room. The installation position should be more than 1.5m above the ground. Before entering the irradiation room, the operator should use the calibration source to check whether the dose meter is normal. 6.4.3 Safety facilities bzxZ.net
The following safety facilities shall be installed in accordance with the provisions of 4.1.3: a) Light and sound signal devices shall be installed to warn personnel inside and outside the irradiation room before the source is raised; 337
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b) Emergency source lowering and door opening buttons are installed in the irradiation room to avoid exposure accidents; c) Drilling source lifting and exit doors and photoelectric interlocking systems are installed to prevent personnel from mistakenly entering the irradiation room and being exposed. d) Automatic source lowering system is installed in case of power failure to avoid irradiation accidents caused by failure of monitoring instruments; e) Source rack forced landing system is installed to release the source rack when some failure occurs in the lifting source; f) Source storage well water level monitoring alarm and replenishment system is installed to avoid the increase of radiation dose level in the irradiation room due to the drop of water level in the source storage well; g) Appropriate measures should be taken to prevent radiation leakage at the entrance and exit, air inlet and exhaust vents and cable ducts through the wall of the irradiation room; h) All detachable shielding plugs in the irradiation room, including the shielding plugs for installing sources, must be interlocked with the central control system so that the source raising operation cannot be carried out when the protective plugs are removed.
6.4.4 Fire prevention requirements
The irradiation room and operation area shall be designed according to the first-level fire prevention design and shall be equipped with fire alarm devices. In case of fire danger, fire alarms can be detected, alarmed and shut down in time, the radiation source can be automatically lowered to a safe position, and effective fire extinguishing measures can be taken in time. 6.4.5 Power supply requirements
The irradiation device must ensure normal power supply. During the operation of the device, when the power outage time exceeds 10s (whether normal or accidental), the source rack must be able to automatically drop to a safe position and the device will automatically shut down. The irradiation device shall be equipped with necessary emergency power supply. When the power outage occurs, the power supply time for the monitoring instruments and safety interlocking devices shall be guaranteed to be no less than 30 minutes to ensure safety. 6.4.6 Earthquake resistance requirements
When building irradiation devices in areas where severe earthquakes may occur, earthquake prevention measures must be taken. Once such a severe earthquake occurs, ensure the integrity of the shielding body, ensure that the storage well does not leak, and ensure that the radioactive source can be safely returned to the storage location. 6.4.7 Ventilation system
According to the designed source quantity and the size of the irradiation room, determine the intake and exhaust air volume to ensure that the concentration of ozone and nitrogen oxides in the air in the irradiation room is lower than the specified value of TJ3679. For irradiation devices with dry source storage greater than 0.37PBq (10,000 Curies), ventilation and heat dissipation measures must be considered for the source well.
The height of the exhaust chimney should be calculated and determined according to the provisions of the national standard GB3095-1996, the harmful gas discharge volume and the environment and meteorological data near the irradiation device.
6.4.8 Water treatment system
All irradiation devices with wet source storage should be equipped with a water treatment system in accordance with the requirements of Appendix A6 to ensure the water quality requirements of the source well. Irradiation devices with more than 37PBq (1 million Curies) must also be equipped with a cooling system. 6.4.9 Other auxiliary systems
In order to ensure the convenience and safety of the operation of the device, the irradiation device should be equipped with a television observation system and other auxiliary systems. 6.5 Design Documents
6.5.1 Contents of Design Documents
The design unit of the irradiation device shall submit the following technical documents to the owner: a) Design specifications and drawings of processes, dosages and protection; b) Specifications for the selection and configuration of major equipment; c) Equipment installation, operation, maintenance instructions and spare parts drawings; d) Building structure drawings and instructions;
e) Electrical and automatic control drawings and instructions;
f) Ventilation system drawings and instructions;
g) Water supply, drainage and water treatment system drawings and instructions. 6.5.2 Modification of Design Documents
After the design documents are proposed, they shall generally not be modified. When modifications are necessary, the design unit shall submit a modification notice. When the owner and the unit entrusted by the owner propose modification requests, they shall be agreed by the design unit, and the designated unit shall submit a modification notice through consultation and signed by the design unit. Modifications that have a significant impact on safety must be approved by the safety authority. 338
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The modification notice should be filed together with the original drawings and materials. 7 Engineering construction and quality supervision
7.1 The construction unit should have a Class B or above construction certificate issued by the state. 7.2 The construction unit should strictly carry out construction according to the construction drawings provided by the design unit. The relevant changes should be accompanied by the modification notice proposed by the design unit and the signature of the design personnel. The construction unit shall not change the drawings without authorization. 7.3 Construction requirements
The irradiation device requires thick concrete walls for shielding protection, has a complex structure, and requires remote control; there are a large number of embedded parts in the protective wall. The following points should be noted during construction: a) Strictly follow the design requirements and make good preparations for construction (including necessary experiments); b) Before pouring concrete in the irradiation room, various embedded parts must be accurately fixed in the required positions, and pouring is allowed only after written approval by the supervisor;
c) The concrete wall of the irradiation room should not have construction joints from -0.30 to +2.00m. It should be poured in layers continuously and vibrated to make it dense without leaving dead corners. In particular, vibration should be strengthened at the embedded parts to avoid defects such as honeycombs, voids, pockmarks and through cracks in the protective wall; d) The construction joint is required to be zigzag or multi-step. When pouring for the second time, the surface dirt should be strictly cleaned to ensure that the new and old are firmly combined without cracks;
e) The construction of the storage well should be carried out strictly according to the requirements of the drawings. Different construction methods can be adopted according to geological conditions, such as caisson or large excavation. Make a waterproof layer to meet the sealing requirements; f) The specific gravity and strength of concrete should be tested first, and the general specific gravity should not be less than 2.3g/cm; the concrete grade of the wall should not be less than 150, and the concrete grade of the foundation should not be less than 200.
7.4 Quality Supervision
In addition to the quality inspection personnel of the construction unit to conduct quality inspection and supervision at any time, the construction unit must have construction supervision personnel to conduct on-site quality supervision and inspection, and make detailed records.
8 Equipment Manufacturing
8.1 Qualification of manufacturing unit
The manufacturing of irradiation equipment process equipment shall be undertaken by units with corresponding qualifications and licenses. 8.2 Basis of equipment manufacturing
8.2.1 Equipment manufacturing shall be based on equipment construction drawings. 8.2.2 The modification of equipment construction drawings shall be carried out by the design unit according to the quality assurance procedure. 8.3 Materials and components
8.3.1 The materials used to manufacture equipment and the components used in equipment shall comply with the provisions of the relevant standards and design technical documents and have quality certificates.
8.3.2 The components used in the equipment shall be inspected piece by piece or tested before they can be used. 8.4 Processing and manufacturing
8.4.1 The limit deviations of the un-toleranced dimensions of the machined surface and the non-machined surface shall be in accordance with the GB1804-m and GB1804-c tolerance grades specified in GB/T1804-92 respectively. 8.4.2 Mechanical damage should be avoided on the steel surface, and obvious sharp scratches should be ground to make them smooth. The grinding depth shall not exceed 10% of the original thickness.
8.4.3 Welding
8.4.3.1 The welding of equipment components must be performed by welders who have passed the examination. 8.4.3.2 For important or complex welded parts, welding process regulations should be formulated according to the requirements of the drawings and the qualified welding processes evaluated by the manufacturing unit. Welders must strictly abide by the regulations. 39
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8.4.3.3 The appearance of the welded surface shall meet the following requirements: a) There shall be no defects such as cracks, pores, isolated pits and slag inclusions on the surface of the weld and heat-affected zone. The slag on the weld and the spatter on both sides must be cleaned up:
h) The depth of the weld undercut shall not exceed 10% of the thickness of the parent material, the continuous length of the undercut shall not exceed 50mm, and the total length of the undercut on both sides of the weld shall not exceed 10% of the length of the weld;
c) The weld and the parent material should have a smooth transition and no obvious irregular shape; d) The thickness of the butt weld after grinding should not be less than the thickness of the parent material. 8.4.4 Processing and manufacturing of stainless steel composite surfaces of source wells 8.4.4.1 The minimum steel plate width in the spliced composite surface shall not be less than half of the entire steel plate (except for the edge), and the entire steel plate shall not be less than 60% of the total area of the well composite surface.
8.4.4.2 Cross-shaped welds shall not appear in the joints of the composite surface. 8.4.4.3 The misalignment of the butt joint of the steel plate shall be less than 0.5mm. The butt weld shall ensure full penetration. 8.4.4.4 The surface of the water-holding side of the composite surface shall be smooth and the weld shall be polished and smooth. If necessary, the overall polishing treatment may be adopted. 8.4.4.5 After the well composite surface is installed in place and welded as one, it shall meet the following requirements: a) Flatness tolerance: 2.5mm per square meter, 15mm for any plane; b) Verticality tolerance: 2:1000 between any two adjacent planes. 8.4.4.6 100% leak detection must be carried out on the welds of the composite surface, and the inspection report shall be submitted. The detection can be carried out by coal Oil leakage test or other inspection methods
8.5 Inspection and acceptance
8.5.1 The quality inspection of equipment manufacturing shall be the responsibility of the manufacturer's specialized institutions and personnel. During the equipment manufacturing process, the processing quality and assembly quality of parts and complete machines shall be inspected in stages. Quality inspection is based on design drawings and their technical requirements. 8.5.2 Before the equipment leaves the factory, the ordering party shall conduct delivery acceptance at the manufacturing site. It mainly includes the following contents: a) Whether the structure, specifications and materials of the equipment conform to the provisions of the design drawings; b) Whether the delivered objects conform to the packing list (delivery details list); c) Whether the equipment packaging and loading methods conform to the provisions of the order contract and the requirements of safe transportation; 8.5.3 After the equipment is installed and debugged on site and qualified, the user shall conduct equipment acceptance. It mainly includes the following contents: a) Whether the equipment installation complies with the provisions of the installation technical requirements; b) Whether the equipment startup and operation are normal;
c) Whether the equipment functions and technical parameters meet the design standards and use requirements. 8.6 Marking, packaging and transportation
8.6.1 Marking
Markings are divided into equipment nameplates and instruction signs. Domestic sales products are marked in Chinese, and export products are marked in English or both Chinese and English. 8.6.1.1 Equipment nameplate
There should be a nameplate with the following contents in the appropriate location of the main equipment: a) Equipment name and model; ||tt ||b) Name of the design unit;
c) Name of the manufacturing unit;
d) Date of shipment.
8.6.1.2 Indicator signs
The display instruments, warning signals, switches, operation buttons, indicator lights, etc. in the equipment must have signs or text marks that explain their display content or operation objects.
8.6.2 Technical documents
The technical documents submitted to the user along with the equipment should include the following: 340
) Operation and maintenance instructions for major equipment: b) Packing list (delivery details list);
c) Factory inspection certificate.
8.6.3 Packaging
GB 17568—1998
8.6.3.1Except for those with specific requirements for packaging in the design technical documents, the manufacturer shall decide whether to package the equipment in the form of complete machine or parts when it leaves the factory.
8.6.3.2For different equipment and parts, different packaging forms such as naked packaging, wrapping, empty boxes or dark boxes can be adopted according to the mode of transportation. Regardless of the type of packaging, it should be ensured that the product is not damaged during transportation, especially for the packaging of vulnerable parts, it must ensure its safety during normal transportation.
8.6.3.3The total number of pieces and piece number should be marked on each package: when it is impossible to write on the naked package, a thin iron sheet or plastic label can be fixed at an appropriate position.
Other markings should also be made when necessary, such as "handle with care", "do not invert", "moisture-proof", etc. If the equipment is transported by rail or shipping, the shipping station (port), arrival station (port) and shipping unit, consignor unit and other shipping marks shall also be indicated. 8.6.4 Transportation
8.6.4.1 The mode of transportation shall be determined by the ordering party and shall be indicated in the ordering contract. 8.6.4.2 If it is transported by road, attention shall be paid to the reasonable loading of the packages, and necessary fixing and other protective measures shall be taken to prevent mechanical damage or rust during transportation.
9 Equipment installation and trial operation
9.1 Equipment installation and commissioning
9.1.1 Equipment installation shall be undertaken by units with corresponding qualifications and licenses. 9.1.2 Equipment installation shall be based on equipment installation documents or equipment construction drawings and relevant materials. 9.1.3 Before installing the equipment, the relevant embedded parts and embedded parts shall be checked one by one, and installation shall be carried out only after they are confirmed to meet the requirements. The handling of non-conforming items shall be approved by the owner and the design unit. 9.1.4 After the equipment is installed, the design and manufacturing units shall debug each system separately according to the debugging outline prepared by the design unit. After the single-compression is qualified, comprehensive debugging shall be carried out.
9.1.5 The passing standard of comprehensive debugging is that the device is simulated to run under heavy load for 48 hours, and the operation rate is not less than 95%. The operation rate is calculated as follows: Operation rate = 8 = —×100%
Where - the sum of the downtime caused by various faults, h. 9.2 Loading radioactive sources
9.2.1 Loading radioactive sources must be carried out after the comprehensive debugging of the device is qualified. 9.2.2 Loading radioactive sources shall be organized and implemented by the user unit under the supervision of the safety protection department. 9.2.3 The user unit shall formulate the detailed operation rules for loading radioactive sources in advance, and shall be reviewed and approved by the safety protection department. 9.2.4 Before loading the source, the operator shall be trained in the operation of loading the source with a simulated source rod and reach a proficient level. 9.2.5 Before hoisting the source tank, the crane and hoisting equipment should be strictly checked, and a heavy object equivalent to the mass of the source tank should be hoisted for inspection. 9.2.6 After the radioactive source is loaded, the position of the source rod and the state of the source rack should be carefully checked. Only after confirming that the source rod is accurately positioned and the source rack is in a safe state can the source lifting operation be carried out.
9.3 Dose test
9.3.1 The dose distribution test of the radiation field and the product should be carried out after the radioactive source is loaded and before the device is put into operation. 9.3.2 The dose distribution test shall be carried out by the unit authorized by the national competent department in accordance with JJG591---1989, and a metrological verification certificate shall be issued. 9.3.3 When the source strength and arrangement of the loaded source change, the dose distribution of the radiation field and the product must be retested. 9.3.4 After the source is loaded, the radiation safety dose test should be carried out in different areas under the source lifting condition to evaluate the shielding protection effect. This test shall be undertaken by an organization authorized by the safety and protection authority, and a test report shall be submitted, and a certificate shall be issued by the authority. 9.4 Trial operation 9.4.1 The trial operation of the irradiation device shall be carried out only after the comprehensive commissioning is qualified, the source is installed and the dose is tested, and the license or approval of the relevant national authorities is obtained. 9.4.2 The user unit shall formulate the trial operation procedures and organize their implementation. 9.4.3 During the trial operation, the operator should make various records as the evaluation basis for the project acceptance. 10 Acceptance of irradiation equipment
After the irradiation device is completed, the superior competent department shall conduct acceptance of the device together with relevant departments. 10.1 Acceptance procedure
a) The user unit and the design unit shall jointly inspect and test the device. After a period of trial operation to confirm that the irradiation device meets the requirements of this standard, the owner shall submit an acceptance application to the competent department; b) After the relevant competent department conducts various tests, it shall provide a test report and issue a "license"; c) The operating personnel (including operation and management) shall obtain a job qualification certificate; d) The competent unit shall organize the review of documents, conduct on-site item-by-item inspections and pass the project acceptance report. 10.2 Acceptance items
a) Civil engineering;
b) Comprehensive equipment test run;
c) Safety test;
d) Project budget.
10.3 Acceptance documents
a) Project approval documents;
b) Design task book;
c) Design drawing documents;
d) Completion report;
e) Trial operation condition report;
f) Safety test report;
g) Dose field test report;
h) Operating procedures and safety rules and regulations;
i) Project final settlement report,
j) Project acceptance report.
11 Operation of irradiation device
11.1 Responsibilities and qualifications of the operating unit and operating personnel11.1.1 The operating unit must have a license for the use of radioactive sources issued by the corresponding management or supervision agency. 11.1.2 The operating unit must be familiar with and ensure the safe operation of the device in accordance with the conditions of the license. 11.1.3 The operating unit must be equipped with 1 to 2 qualified personnel to be responsible for the safety of the irradiation device during use and operation. He must have the following skills:
a) Have received theoretical training and have the necessary knowledge of the ionizing radiation characteristics of the work he is engaged in; b) Be familiar with the structure and performance of the equipment and have a relatively thorough understanding of the emergency measures for handling accidents; ℃) Understand and master the relevant regulations and operating procedures of the equipment issued by the state and relevant competent authorities. 11.7.4 The operator shall be a person who is in good health and has obtained a work permit approved by the relevant management and supervision departments. 11.1.5 The operator must be familiar with: the basic structure, operation and maintenance of the irradiation device, the principles and actual operation of radiation protection; normal operation 342
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