Standard No.:	EJ 380-1989
English Name:	Design Provisions for Radiation Protection of Open Radioactive Material Laboratories
Chinese Name:	开放型放射牲物质实验室辐射防护设计规范
Professional Classification:	EJ    Professional Standard - Nuclear Industry
Issued on:	1989-03-24
Implemented on:	1989-10-1
Status:	valid
Target Language:	English
File Format:	PDF
Word Count:	6500 words
Translation Price(USD):	300.0
Delivery:	via email in 1 business day

EJ 380-1989 Code for radiation protection design of open radioactive material laboratories 1 Subject content and application scope This standard specifies the radiation protection requirements to be observed in the design of open radioactive material laboratories (hereinafter referred to as “open laboratories”), with the objective of ensuring the health and safety of working personnel and nearby residents, as well as the protection of the environment from the design stage. This standard is applicable to the radiation protection design of open radioactive material laboratories engaged in the production and application of radioisotopes. It may also serve as a reference for radiation protection design in expansion or modification projects of existing facilities. This standard is not applicable to the radiation protection design of laboratories in spent fuel reprocessing plants or in uranium mining and metallurgy systems. 2 Normative references GB 8703 Regulations for radiation protection GB 4792 Basic health standards for radiological protection GB 11806 Regulations for the safe transport of radioactive material EJJ 6 Regulations for criticality safety in processing and handling of fissile materials 3 Terms 3.1 open laboratory a laboratory, consisting of one or more work areas, in which unsealed radioactive materials are handled, the laboratory is equipped with hot cells, shielded boxes with tongs, glove boxes, fume hoods, and other devices, as well as auxiliary facilities necessary for the normal operation of the laboratory 3.2 open radioactive work work involving unsealed radioactive materials, in which normal operations performed on benches or within enclosures may result in contamination of the workplace or the surrounding environment 3.3 zoning of open laboratory to control contamination, the laboratory is divided into several zones in the design stage, with different zones subject to different design requirements 3.4 White Zone (Zone I) a zone within the laboratory where radioactive work is not conducted and where, under normal conditions, no radioactive contamination is present; White Zones include: offices, meeting rooms, rest rooms, “cold” workrooms (such as reagent or pharmaceutical rooms), “cold” laboratories, etc. 3.5 Green Zone (Zone II) a work zone within the laboratory where radioactive materials are handled under containment, contamination may occur in the event of an incident, but can be promptly detected and removed; Green Zones include: operation rooms for hot cells, shielded boxes with tongs, and glove boxes, as well as rooms used for storing sealed containers 3.6 Orange Zone (Zone III) a zone within the laboratory where working personnel do not remain routinely and shall only enter for operations such as decontamination, maintenance, or sampling; in this zone, contamination may occur during normal operation, but is generally removable; Orange Zones include: maintenance areas for hot cells, shielded boxes with tongs, and glove boxes, temporary storage rooms for radioactive contaminants, decontamination rooms, etc. 3.7 Red Zone (Zone IV) a zone within the laboratory where radioactive materials are present, and where external exposure is high and airborne contamination is severe during operation; Red Zones include: the interiors of hot cells, shielded boxes with tongs and glove boxes, and irradiation chambers 4 General principles and main tasks for radiation protection design of open laboratories 4.1 When designing open laboratory facilities, the following principle must be observed, that is, it must be ensured that the radiation doses received by personnel working inside the facilities, working personnel outside the facilities, personnel in adjacent areas, and the general public do not exceed the dose limits established for them. Efforts shall be made to achieve optimization of radiation protection, maintaining working personnel exposure at levels that are as low as reasonably achievable (ALARA).

Contents 1 Subject content and application scope 2 Normative references 3 Terms 4 General principles and main tasks for radiation protection design of open laboratories 5 Dose limits and principles for control of radiation exposure 6 Classification of open laboratories and division of workplaces 7 Site selection and general layout of open laboratories 8 Zoning and room layout of open laboratories 9 Personnel movement and material flow in open laboratories 10 Sealing and ventilation of radioactive materials in open laboratories 11 Design of equipment and water supply and drainage in open laboratories 12 Treatment of radioactive waste in open laboratories 13 Radiation shielding design in open laboratories 14 Design of radiation monitoring in open laboratories 15 Other safety technical measures Annex A Characteristics of radiation shielding materials (Supplementary)