Ex) Article Title, Author, Keywords
Ex) Article Title, Author, Keywords
Progress in Medical Physics 2020; 31(4): 194-204
Published online December 31, 2020
https://doi.org/10.14316/pmp.2020.31.4.194
Copyright © Korean Society of Medical Physics.
Na Hye Kwon1 , Young Jae Jang2,4 , Dong Wook Kim1 , Dong Oh Shin3 , Kum Bae Kim4 , Jin Sung Kim1 , Sang Hyoun Choi4
Correspondence to:Sang Hyoun Choi
(sh524mc@gmail.com)
Tel: 82-2-970-1590
Fax: 82-2-970-2412
This study investigated and analyzed the Korean and international status of radioactive waste management for medical linear accelerators (linacs) and proceed prior research to suggest radiation safety regulations and guidelines for the safe use of radiation. We analyzed the number of linacs installed in the radiation oncology departments of 103 institutions. In addition, we analyzed the procedures and standards for disposal in Korea and foreign countries. For foreign countries, we analyzed the status based on reports from the United States, Japan, Europe, and Canada. A total of 182 linacs are installed in Korea and 95% of them use more than 10 MV of energy. In Korea, standards for managing radioactive waste from a linac, disposal procedures, and clearance criteria have yet to be established. Therefore, radioactive waste is disposed of in different ways depending on the hospitals where they originate. Japan, the US, and Canada have recommended clearance levels and procedures for linacs. Other countries have provided management guidelines for research or large-scale accelerators, but not for medical purposes. In this study, we investigated the management of radioactive waste from medical linacs in Korea and abroad. Several foreign countries have suggested a clearance level and criteria for disposing of waste storage drums. For the safe management of medical linacs, it is necessary to establish safety management regulations. In Korea, standards for disposal, such as radiation or dose limits, are required for medical linacs. A system for clearance when disposing at a medical institution should be created.
KeywordsLinear accelerator, Disposal, Radioactive waste, Management, Clearance
The radiotherapy device industry is growing as part of the development of radiotherapy technology. In particular, radiation treatment technology that uses high-energy radiation of 6 to 15 MV or more is rapidly being incorporated by medical institutions; interest in the use of safe radiation therapy devices is also increasing while improving the quality of life of patients treated with high-precision radiation. Currently, most institutions in Korea and abroad use an 8–15 MV high-energy linear accelerator (linac), so using technology based on preceding radiation safety regulations is crucial. In Korea, however, it is difficult to systematically manage radioactive waste because of the absence of guidelines for disposal or replacement of linacs due to aging or failed parts.
NCRP (National Council on Radiation Protection and Measurement) 79 and IAEA (International Atomic Energy Agency) TECDOC 1183 outlined the need to manage radioactive waste from internal components, such as a target, collimator, flattening filter, and ion chamber when dismantling a linac. The IAEA TECDOC 1183 showed that a possibility exists for the radiation of surrounding substances when using an accelerator of 10 MV or more and that the head parts are activated during the disassembly of an linac; therefore, an evaluation of the activation should be conducted [1]. According to NCRP 79, when energy of 10 MV or more is used, a radiation evaluation is required and activation occurs in the head parts, such as the target, collimator, and flattening filter [2]. NCRP 151 states that when a high-energy accelerator of 10 MV or more is used, radionuclides may be generated by the radiation of neutrons and gamma rays from the components of linac, which may result in exposure to patients and staff [3].
According to data from the Workshop for Improving Safety Management in the Medical Field, a total of 11 linacs were replaced from 2013 to 2017 and a total of 17 linacs were discarded [4]. On average, two or more linacs are replaced or discarded every year, although the relevant regulations and standards have yet to be established.
In accordance with the Nuclear Safety Commission Notice No. 2017–65, standards and clearance levels are stipulated according to the allowable concentration of nuclides [5]. However, information on radionuclides generated during the process of discarding a linac is limited and variables, such as the number of patients, treatment methods, and treatment device models, change depending on the facility. Due to a lack of standardized regulations for disposal or management, an urgent need exists for the development of a management plan for the disposal of radioactive waste.
The operational period of a linac is typically 10 to 15 years and linacs are replaced or discarded for various reasons, such as aging parts, failure of major parts, and the introduction of new treatment devices. When disposing of equipment, it is recommended to report this to the Korea Institute of Nuclear Safety (KINS) and dispose of or store waste when considering the activation. In addition, discarding the linac after measurements have been taken and clearance is possible is recommended, although standards and procedures (e.g., clearance and consignment disposal) have yet to be established. In this study, to establish a basis for safety management procedures and regulations when replacing or discarding a medical linac, we analyzed current practices for managing radioactive waste from medical linacs in Korea and other countries.
There are 103 hospitals using a linac in Korea, with a total of 182 linacs installed. Fig. 1 shows the number of linacs according to the year they were installed from 1992 to 2020. A total of 66 linacs were installed between 1992 and 2010. Considering that the average life of a linac is 10 to 15 years, it is expected that their replacement or disposal owing to new installations will rapidly increase.
Fig. 2 shows an analysis of the energy used by installed linac equipment. Approximately 95% of linacs use more than 10–15 MV of energy and more than 95% of linacs use this energy to generate an activation product.
In Korea, no legally stipulated procedures or standards exist for linac disposal and thus disposal methods vary in different hospitals. The Nuclear Safety and Security Commission of Korea and the Korea Radioactive Waste Agency create regulations for the disposal of radioactive materials, such as radioisotopes.
Some hospitals store the entire head part of the radioactive linac in a radioactive waste storage facility at the hospital after detachment. In addition, several parts are used as education-assistive tools or are collected by replacement companies without evaluation of the radioactive concentration/contamination when replaced.
Some hospitals have applied a clearance or consignment disposal process by hiring a disposal company. The related disposal procedures are shown in Fig. 3, which shows that after shutdown of a linac, the equipment should be dismantled immediately or within one to two months after shutdown. When the linac is disposed, the disposal company measures the surface dose rate for each component by using a survey meter. When relocating or disposing of equipment through a company, these processes proceed without measuring the dose rate. Waste with a dose rate below the level of the background level of the dose rate (radiation) is disposed of as general waste and waste above the background is stored in the radioisotope waste storage facility of the hospital.
Currently, when disposing of a medical linac with a disposal company in Korea, a document on measures for disposing of a radiation-generating device is provided, as shown in Fig. 4. The document includes information on the disposal equipment, removal date, measures taken, results of the dose rate measurement, information on the detector used, and the calibration date. In addition, as shown on the Fig. 4b, the dose rate is measured using a survey meter for each component of the discarded linac. When dismantling, the surface dose is measured and recorded for each major component and reported to the KINS.
The US Department of Energy (DOE) published technical standards in 2016 to support the control, clearance, and release of personal property (materials, equipment, and items) from an accelerator, accelerator facilities, and modules. In this report, based on DOE Directive Order 458.1 and ANSI N13.12-2013, regulations regarding the requirements for radiological protection of the air and environment are described [6–8]. The DOE report is based on large accelerators, such as the SLAC (Stanford Linear Accelerator Center), and suggests clearance standards, process knowledge, and measurement methodology.
The total effective dose limit is set at 0.01 mSv/y for the disposal of properties with residual radioactivity as stipulated in O 458.1 and 10 CFR Part 835.1101. The DOE report presented the screening level and dose limit for surface and volumetric activity based on 0.01 mSv/y [9].
The DOE report recommends that process knowledge is used to determine whether radioactivity remains in the various parts of a linac during disposal. Process knowledge indicates whether a substance can be radiated or contaminated and classified as general knowledge or specific knowledge. General process knowledge includes information that is equally applicable to most accelerator installations with similar properties or operations, such as beam energy and particle types.
When disposing of a linac, a document should be produced that contains the contents of its work history, procedures, and measurements, including process knowledge, as shown in Table 1.
Table 1 Contents of general program documents and documents related to clearance
General program documentation | Additional documents for clearance |
---|---|
Related regulations and standards | Additional process knowledge used in the measurement process during clearance (beam parameters and operating conditions, materials, etc.) |
Fig. 5 shows the linac disposal process [10]. After the linac is turned off, the head part is detached and its multileaf collimator (MLC), collimator head, gantry head, and bending magnet are discarded. Because the degree of activation varies according to the energy used in the linac, the parts must be disassembled and handled only after the recommended length of time. Components should not be removed until the dose rate is less than 50 µSv/h (5 mrem/h) at a distance of 1 ft (30 cm) from the surface of the linac.
• Accelerators using 10–14 MV X-ray energy: at least 1 hour after beam shutdown
• Accelerators operating above 15 MV X-ray energy: a longer attenuation period is recommended, typically 12–24 hours after beam shutdown
The list of hazardous substances and substances that should be removed from the linac gantry head, including non-radioactive parts, is as follows:
• Sealed components containing oil that may contain printed circuit boards (PCBs) (e.g., capacitors, transformers)
• PCBs with a surface area of 10 cm2 or larger
• Plastic containing brominated flame retardant
• External electric cable
• Ingredients containing radioactive substances
• Electrolytic capacitors containing substances of concern (height ≥25 mm, diameter ≥25 mm)
• Beryllium (bending magnet beam exit window)
• Radiation shielding lead (bending magnet, collimator, carousel) and lead solder
• Metal surfaces, sheet metal, and hardware surfaces
Regulations for the dismantling and disposal of radioactive waste are outlined in the Act on the Regulation of Radioactive Isotopes (Atomic Energy Regulatory Authority), the Medical Law/Medical Law Enforcement Rules (Ministry of Health, Labor, and Welfare), the Labor Safety and Sanitation Act, and the Radio Law (Ministry of Internal Affairs and Communications). In Japan, regulations and facility standards, such as storage, disposal, incineration, and disposal of radioactive waste, are applied in the same manner as applied to waste contaminated by radioisotopes [11].
1) Procedure for replacement and abolitionThe procedures followed during the preparation stage for replacement of equipment or abolition of the facility is shown in Fig. 6. Japan recommends forming a dedicated group to replace equipment, as well as an additional review group within an institution that uses a linac. The institution that uses the linac investigates the status of the facility and conducts an overall estimate of the work to be performed and the cost. Next, a procedure for finalizing a disposal plan should be created by making decisions on institutional policies, the division of roles, scheduling, and budget.
When replacing or disposing of equipment, the user should classify and dismantle the radioactive components (regulated parts). In addition, the components are divided into those that can be reused and those to be disposed of, as shown in Fig. 7. Equipment to be reused is transported to a licensed user at another facility. Transportation immediately after dismantling or storage in a radioactive waste storage facility are optional. Equipment to be discarded is either immediately disposed of without first storing it in a storage disposal facility or it is stored similarly to equipment that is reused.
The procedure for radiation measurement during disassembly of a linac is shown in Fig. 8. Radiation measurements related to the handling of radioactive waste should be conducted when disposing of regulated activation products, for products to be taken out of the radiation-controlled area, and for transport. The dose rate is measured at a distance of 1 cm from the equipment part by using a survey meter and the dose rate is converted into Bq according to the conversion table used in Japan. After determining the reference dose of the radionuclides, the components are divided and stored in a drum.
In addition, if storage and disposal facilities are installed, periodic dose measurements are required. The types of measurements are divided into cases that the medical institution directly conducts and cases that are entrusted to a professional contractor. In addition, the final evaluation should be conducted by the medical institution even in the case of consignment.
The European Commission provides recommendations on the “Practical use of the concepts of clearance and exemption” in accordance with the Radiation Protection Report 122 as published in 2000 [12]. In principle, waste should not be generated and resources should be reused; however, radioactive materials are classified as exceptions and disposal is recommended.
In the case of radioactive waste, it is not necessary to report radioactive material with an activity concentration below the specific exemption for nuclides and prior approval for disposal is not required. The standard for clearance of radioactive waste is 10 µSv/y for individuals and 1 man-Sv/y for collective doses. The standards for clearance follow the IAEA Safety Series 89, but the Commission has difficulty linking dose standards for authorization and disposal with individual exposure. Therefore, exposure scenarios are typically constructed to obtain individual doses [13].
1) Linac disposal management in GermanyGermany’s Radiation Protection Committee recommends clearance criteria for accelerators based on a report, “Clearance of accelerators and the removal of accelerator parts from radiation protection areas,” which was published in 2009 [14]. Dismantling and disposal should be performed based on the history of an accelerator, operating time, and component materials. In particular, the establishment of a disposal standard for an accelerator is proposed by considering the nuclides of each component. However, as in Korea, no clear procedures and regulations exist, but these will be considered in the next revision of the radiation protection regulations.
In accordance with the treaty (2016/C 203/01) published in 2016 by the European Atomic Energy Community (Euratom), European Union (EU) countries, such as Germany, Sweden, the United Kingdom, and France, have prepared disposal plan reports for when radioactive waste is generated [15]. Each member state must provide the European Committee with a radioactive waste disposal plan and determine whether the implementation of the plan could result in water, soil, or radioactive contamination. The reports must include information about the facility from which the waste originated, the distance to the EU member state closest to the facility, whether the waste is stored prior to transportation, and whether it is within the dose limits [16].
In Canada, to dismantle a facility where a medical linac is used, a permit application is first submitted, as well as a plan of action. As shown in Table 2, a final decommissioning report, including a decommissioning plan, information on generated radioactive materials, preparation for disposal of other hazardous substances, and other factors, should be prepared and submitted to the Canadian Nuclear Safety Commission (CNSC). At this time, Class II equipment is regulated as follows:
Table 2 Content of final medical linear accelerator dismantling report in Canada
Outline of the decommissioning plan | Decommissioning schedule |
Manpower qualification and training | Name and title of the person responsible for decommissioning plan |
Estimation of the type, activity, and radiation dose of nuclear materials | The properties, types, and radioactivity of radioactive materials or contamination information of the nuclear facility |
Disposal of Class II regulated equipment, nuclear and hazardous materials | Proposed final disposal method for the major components of the accelerator (e.g., sale or disposal, return to the manufacturer, transfer to another facility for potential reuse, or kept by the license holder for future reuse) |
• Particle accelerators with beam energy of less than 50 MeV that are capable of producing nuclear energy
• Irradiators using nuclear material of 1,015 Bq or higher
• Irradiators requiring shielding because the dose rate at 1 m exceeds 1 cGy/min
• External treatment devices or remote brachytherapy devices (afterloaders) using a radioactive source
1) Disposal method in CanadaCanada disposes of parts differently depending on the level of activation of products from medical linacs and the possession of a CNSC license. In the case of a permitted facility with a CNSC license, the linac is returned to its manufacturer. If the facility has no license, the accelerator or its components are transferred to a repair company. Except for the above examples, waste is typically disposed according to clearance criteria.
Other than for a return to the manufacturer (in the case of a transfer to a repair company) or when using general waste disposal methods, the requirements of section 5.1 of the Nuclear Substances and Radiation Device Regulations must be satisfied [17]. In the absence of a license, a linac can be disposed of if the radioactivity or concentration of radioactive nuclear material does not exceed standard guidelines. In Canada, a dose rate-based measurement method is recommended. In the case of medical accelerators, conditional clearance is allowed if the measurement is less than 0.5 µSv/h when measured at 5 cm from the accessible surface of the component [18].
After disassembly of the linac, the classified radioactive parts must be stored in a storage box that conforms to a certain standard or disposed of after storage. In countries that recommend storage boxes for storing radioactive waste and linac parts, we classified the standards of Japan’s Society Standard Technical Reports and reports from Varian Co., as shown in Table 3 [11]. The basic standard is 50 L in Japan and 210 L in the United States. In Japan, an application is submitted to borrow a waste storage container. A 50 L drum can be borrowed for free and 210 L drums are rented for a fee. At this time, four 50-L drums are typically used. In the United States, 55 gallon (210 L) drums and the insertion of foam are required for the storage and management of radioactive parts. It is recommended that three 5-gallon (19 L) steel drums are used for other parts and that two plastic tarps are used to protect the floor and collect contaminated dust. Wooden pallets can be used if necessary.
Table 3 Comparison of medical linac radioactive waste storage containers
Country | Japan | USA |
---|---|---|
Standard | 50 L | 210 L (55 gallons) |
Other information | Fill out the application for borrowing of waste containers | 210 L drum and inserted foam are required as standard for storage and maintenance of radioactive components |
The clearance criteria for radioactive waste from the medical linac and the method of evaluating the activation differ, as shown in Table 4. As a detector for evaluating radioactive waste, Japan, the United States, and Canada typically use a survey meter. The location of the measurement is at a distance of 1 cm in Japan and the United States, but 5 cm in Canada. The clearance criterion is 10 µSv/y in all three countries, which is the same as in Korea. Canada allows a clearance of 0.5 µSv/h or less. This is a calculated value assuming that the annual allowance standard is an average working time of 40 hours and that 15 linac parts are managed per year.
Table 4 Criteria for evaluation and clearance of radioactive waste in the linac
Country | Japan | USA | Canada |
---|---|---|---|
Measuring instrument | NaI(Tl) scintillation survey meter | NaI(Tl) scintillation survey meter, Geiger–Muller (GM) counter Counter, etc. | Survey meter |
Measuring location | 1 cm distance | 1 cm distance | 5 cm distance |
Clearance criteria | 10 µSv/y | 10 µSv/y (1 mrem/y) | 0.5 µSv/h (10 µSv/y) |
Other | Calculate the amount of radioactivity (Bq) based on the dose rate (µSv/h) measured (weight measurement and conversion factor applied) | Effective distance of scintillator instrument: 1 cm from the surface | When converting to the effective dose, use the 30 cm standard (distance inverse square law) |
SLAC, Stanford Linear Accelerator Center.
In this study, to establish safety regulation guidelines and procedures for the management of radioactive waste from medical linacs in Korea, the current management practices in Korea and abroad were investigated.
As a result of this investigation, it was shown that standards and procedures for disposing of a linac have yet to be established in Korea. Because activated waste generated by a medical linac is not classified as radioactive waste, the Korean radioactive waste agency, a facility that disposes and manages waste, handles only radioisotopes.
Because no legally prescribed procedure or standard for disposing of a linac exists, it was found that most medical institutions do not have safety management regulations. In addition, radioactive waste is collected by companies without following any procedures or guidelines or the head of medical linacs are stored in the waste storage areas at hospitals. It was shown that the institutions or individual owners in Korea collect the waste by using a company but without any action taken at medical institutions.
Japan, the United States, and Canada have guidelines to treat radioactive waste that is produced by a linac. Japan has regulated radioactive cargo from linacs in the same way that radioactive isotopes are regulated, and the United States and Canada have proposed clearance criteria for radioactive waste. However, most reports from the EU, the International Atomic Energy Agency, and the United States have provided management guidelines for research or large-scale accelerators, but not for linacs.
For the safe management of a medical linac, it is necessary to establish safety management regulations for radioactive waste produced at medical institutions.
First, before dismantling the linac, a dismantling and disposal plan must be prepared and reported to the KINS as recommended by European nations, such as Germany. In addition, medical institutions should form a dedicated team that will perform the work, as is done to Japan. For the process of disposal, as suggested by the processes performed Japan, the United States, and Canada, the dose rate of the components is measured using a survey meter and the general and radioactive waste should be classified according to the 0.5 μSv/h standard. In addition, the sorted parts must be stored or transported in standardized drums 50 or 210 L in size.
In Korea, standards for disposal, such as dose limits, are required for medical linacs. As in other countries, a system for the disposal of a linac according to a clear procedure should be established.
This work was supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) using the financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2003013).
The authors have nothing to disclose.
All relevant data are within the paper and its Supporting Information files.
Conceptualization: Na Hye Kwon, Sang Hyoun Choi. Data curation: Na Hye Kwon. Funding acquisition: Sang Hyoun Choi. Investigation: Jin Sung Kim. Methodology: Kum Bae Kim, Dong Wook Kim. Project administration: Sang Hyoun Choi. Validation: Dong Oh Shin. Visualization: Young Jae Jang. Writing–original draft: Na Hye Kwon. Writing–review & editing: Nahye Kwon, Sang Hyoun Choi.
Progress in Medical Physics 2020; 31(4): 194-204
Published online December 31, 2020 https://doi.org/10.14316/pmp.2020.31.4.194
Copyright © Korean Society of Medical Physics.
Na Hye Kwon1 , Young Jae Jang2,4 , Dong Wook Kim1 , Dong Oh Shin3 , Kum Bae Kim4 , Jin Sung Kim1 , Sang Hyoun Choi4
1Department of Radiation Oncology, Yonsei Cancer Center, Yonsei University College of Medicine, Seoul, 2Department of Accelerator Science, Korea University, Sejong, 3Department of Radiation Oncology, Kyung Hee University Hospital, 4Research Team of Radiological Physics & Engineering, Korea Institute of Radiological & Medical Sciences, Seoul, Korea
Correspondence to:Sang Hyoun Choi
(sh524mc@gmail.com)
Tel: 82-2-970-1590
Fax: 82-2-970-2412
This study investigated and analyzed the Korean and international status of radioactive waste management for medical linear accelerators (linacs) and proceed prior research to suggest radiation safety regulations and guidelines for the safe use of radiation. We analyzed the number of linacs installed in the radiation oncology departments of 103 institutions. In addition, we analyzed the procedures and standards for disposal in Korea and foreign countries. For foreign countries, we analyzed the status based on reports from the United States, Japan, Europe, and Canada. A total of 182 linacs are installed in Korea and 95% of them use more than 10 MV of energy. In Korea, standards for managing radioactive waste from a linac, disposal procedures, and clearance criteria have yet to be established. Therefore, radioactive waste is disposed of in different ways depending on the hospitals where they originate. Japan, the US, and Canada have recommended clearance levels and procedures for linacs. Other countries have provided management guidelines for research or large-scale accelerators, but not for medical purposes. In this study, we investigated the management of radioactive waste from medical linacs in Korea and abroad. Several foreign countries have suggested a clearance level and criteria for disposing of waste storage drums. For the safe management of medical linacs, it is necessary to establish safety management regulations. In Korea, standards for disposal, such as radiation or dose limits, are required for medical linacs. A system for clearance when disposing at a medical institution should be created.
Keywords: Linear accelerator, Disposal, Radioactive waste, Management, Clearance
The radiotherapy device industry is growing as part of the development of radiotherapy technology. In particular, radiation treatment technology that uses high-energy radiation of 6 to 15 MV or more is rapidly being incorporated by medical institutions; interest in the use of safe radiation therapy devices is also increasing while improving the quality of life of patients treated with high-precision radiation. Currently, most institutions in Korea and abroad use an 8–15 MV high-energy linear accelerator (linac), so using technology based on preceding radiation safety regulations is crucial. In Korea, however, it is difficult to systematically manage radioactive waste because of the absence of guidelines for disposal or replacement of linacs due to aging or failed parts.
NCRP (National Council on Radiation Protection and Measurement) 79 and IAEA (International Atomic Energy Agency) TECDOC 1183 outlined the need to manage radioactive waste from internal components, such as a target, collimator, flattening filter, and ion chamber when dismantling a linac. The IAEA TECDOC 1183 showed that a possibility exists for the radiation of surrounding substances when using an accelerator of 10 MV or more and that the head parts are activated during the disassembly of an linac; therefore, an evaluation of the activation should be conducted [1]. According to NCRP 79, when energy of 10 MV or more is used, a radiation evaluation is required and activation occurs in the head parts, such as the target, collimator, and flattening filter [2]. NCRP 151 states that when a high-energy accelerator of 10 MV or more is used, radionuclides may be generated by the radiation of neutrons and gamma rays from the components of linac, which may result in exposure to patients and staff [3].
According to data from the Workshop for Improving Safety Management in the Medical Field, a total of 11 linacs were replaced from 2013 to 2017 and a total of 17 linacs were discarded [4]. On average, two or more linacs are replaced or discarded every year, although the relevant regulations and standards have yet to be established.
In accordance with the Nuclear Safety Commission Notice No. 2017–65, standards and clearance levels are stipulated according to the allowable concentration of nuclides [5]. However, information on radionuclides generated during the process of discarding a linac is limited and variables, such as the number of patients, treatment methods, and treatment device models, change depending on the facility. Due to a lack of standardized regulations for disposal or management, an urgent need exists for the development of a management plan for the disposal of radioactive waste.
The operational period of a linac is typically 10 to 15 years and linacs are replaced or discarded for various reasons, such as aging parts, failure of major parts, and the introduction of new treatment devices. When disposing of equipment, it is recommended to report this to the Korea Institute of Nuclear Safety (KINS) and dispose of or store waste when considering the activation. In addition, discarding the linac after measurements have been taken and clearance is possible is recommended, although standards and procedures (e.g., clearance and consignment disposal) have yet to be established. In this study, to establish a basis for safety management procedures and regulations when replacing or discarding a medical linac, we analyzed current practices for managing radioactive waste from medical linacs in Korea and other countries.
There are 103 hospitals using a linac in Korea, with a total of 182 linacs installed. Fig. 1 shows the number of linacs according to the year they were installed from 1992 to 2020. A total of 66 linacs were installed between 1992 and 2010. Considering that the average life of a linac is 10 to 15 years, it is expected that their replacement or disposal owing to new installations will rapidly increase.
Fig. 2 shows an analysis of the energy used by installed linac equipment. Approximately 95% of linacs use more than 10–15 MV of energy and more than 95% of linacs use this energy to generate an activation product.
In Korea, no legally stipulated procedures or standards exist for linac disposal and thus disposal methods vary in different hospitals. The Nuclear Safety and Security Commission of Korea and the Korea Radioactive Waste Agency create regulations for the disposal of radioactive materials, such as radioisotopes.
Some hospitals store the entire head part of the radioactive linac in a radioactive waste storage facility at the hospital after detachment. In addition, several parts are used as education-assistive tools or are collected by replacement companies without evaluation of the radioactive concentration/contamination when replaced.
Some hospitals have applied a clearance or consignment disposal process by hiring a disposal company. The related disposal procedures are shown in Fig. 3, which shows that after shutdown of a linac, the equipment should be dismantled immediately or within one to two months after shutdown. When the linac is disposed, the disposal company measures the surface dose rate for each component by using a survey meter. When relocating or disposing of equipment through a company, these processes proceed without measuring the dose rate. Waste with a dose rate below the level of the background level of the dose rate (radiation) is disposed of as general waste and waste above the background is stored in the radioisotope waste storage facility of the hospital.
Currently, when disposing of a medical linac with a disposal company in Korea, a document on measures for disposing of a radiation-generating device is provided, as shown in Fig. 4. The document includes information on the disposal equipment, removal date, measures taken, results of the dose rate measurement, information on the detector used, and the calibration date. In addition, as shown on the Fig. 4b, the dose rate is measured using a survey meter for each component of the discarded linac. When dismantling, the surface dose is measured and recorded for each major component and reported to the KINS.
The US Department of Energy (DOE) published technical standards in 2016 to support the control, clearance, and release of personal property (materials, equipment, and items) from an accelerator, accelerator facilities, and modules. In this report, based on DOE Directive Order 458.1 and ANSI N13.12-2013, regulations regarding the requirements for radiological protection of the air and environment are described [6–8]. The DOE report is based on large accelerators, such as the SLAC (Stanford Linear Accelerator Center), and suggests clearance standards, process knowledge, and measurement methodology.
The total effective dose limit is set at 0.01 mSv/y for the disposal of properties with residual radioactivity as stipulated in O 458.1 and 10 CFR Part 835.1101. The DOE report presented the screening level and dose limit for surface and volumetric activity based on 0.01 mSv/y [9].
The DOE report recommends that process knowledge is used to determine whether radioactivity remains in the various parts of a linac during disposal. Process knowledge indicates whether a substance can be radiated or contaminated and classified as general knowledge or specific knowledge. General process knowledge includes information that is equally applicable to most accelerator installations with similar properties or operations, such as beam energy and particle types.
When disposing of a linac, a document should be produced that contains the contents of its work history, procedures, and measurements, including process knowledge, as shown in Table 1.
Table 1 . Contents of general program documents and documents related to clearance.
General program documentation | Additional documents for clearance |
---|---|
Related regulations and standards | Additional process knowledge used in the measurement process during clearance (beam parameters and operating conditions, materials, etc.) |
Fig. 5 shows the linac disposal process [10]. After the linac is turned off, the head part is detached and its multileaf collimator (MLC), collimator head, gantry head, and bending magnet are discarded. Because the degree of activation varies according to the energy used in the linac, the parts must be disassembled and handled only after the recommended length of time. Components should not be removed until the dose rate is less than 50 µSv/h (5 mrem/h) at a distance of 1 ft (30 cm) from the surface of the linac.
• Accelerators using 10–14 MV X-ray energy: at least 1 hour after beam shutdown
• Accelerators operating above 15 MV X-ray energy: a longer attenuation period is recommended, typically 12–24 hours after beam shutdown
The list of hazardous substances and substances that should be removed from the linac gantry head, including non-radioactive parts, is as follows:
• Sealed components containing oil that may contain printed circuit boards (PCBs) (e.g., capacitors, transformers)
• PCBs with a surface area of 10 cm2 or larger
• Plastic containing brominated flame retardant
• External electric cable
• Ingredients containing radioactive substances
• Electrolytic capacitors containing substances of concern (height ≥25 mm, diameter ≥25 mm)
• Beryllium (bending magnet beam exit window)
• Radiation shielding lead (bending magnet, collimator, carousel) and lead solder
• Metal surfaces, sheet metal, and hardware surfaces
Regulations for the dismantling and disposal of radioactive waste are outlined in the Act on the Regulation of Radioactive Isotopes (Atomic Energy Regulatory Authority), the Medical Law/Medical Law Enforcement Rules (Ministry of Health, Labor, and Welfare), the Labor Safety and Sanitation Act, and the Radio Law (Ministry of Internal Affairs and Communications). In Japan, regulations and facility standards, such as storage, disposal, incineration, and disposal of radioactive waste, are applied in the same manner as applied to waste contaminated by radioisotopes [11].
1) Procedure for replacement and abolitionThe procedures followed during the preparation stage for replacement of equipment or abolition of the facility is shown in Fig. 6. Japan recommends forming a dedicated group to replace equipment, as well as an additional review group within an institution that uses a linac. The institution that uses the linac investigates the status of the facility and conducts an overall estimate of the work to be performed and the cost. Next, a procedure for finalizing a disposal plan should be created by making decisions on institutional policies, the division of roles, scheduling, and budget.
When replacing or disposing of equipment, the user should classify and dismantle the radioactive components (regulated parts). In addition, the components are divided into those that can be reused and those to be disposed of, as shown in Fig. 7. Equipment to be reused is transported to a licensed user at another facility. Transportation immediately after dismantling or storage in a radioactive waste storage facility are optional. Equipment to be discarded is either immediately disposed of without first storing it in a storage disposal facility or it is stored similarly to equipment that is reused.
The procedure for radiation measurement during disassembly of a linac is shown in Fig. 8. Radiation measurements related to the handling of radioactive waste should be conducted when disposing of regulated activation products, for products to be taken out of the radiation-controlled area, and for transport. The dose rate is measured at a distance of 1 cm from the equipment part by using a survey meter and the dose rate is converted into Bq according to the conversion table used in Japan. After determining the reference dose of the radionuclides, the components are divided and stored in a drum.
In addition, if storage and disposal facilities are installed, periodic dose measurements are required. The types of measurements are divided into cases that the medical institution directly conducts and cases that are entrusted to a professional contractor. In addition, the final evaluation should be conducted by the medical institution even in the case of consignment.
The European Commission provides recommendations on the “Practical use of the concepts of clearance and exemption” in accordance with the Radiation Protection Report 122 as published in 2000 [12]. In principle, waste should not be generated and resources should be reused; however, radioactive materials are classified as exceptions and disposal is recommended.
In the case of radioactive waste, it is not necessary to report radioactive material with an activity concentration below the specific exemption for nuclides and prior approval for disposal is not required. The standard for clearance of radioactive waste is 10 µSv/y for individuals and 1 man-Sv/y for collective doses. The standards for clearance follow the IAEA Safety Series 89, but the Commission has difficulty linking dose standards for authorization and disposal with individual exposure. Therefore, exposure scenarios are typically constructed to obtain individual doses [13].
1) Linac disposal management in GermanyGermany’s Radiation Protection Committee recommends clearance criteria for accelerators based on a report, “Clearance of accelerators and the removal of accelerator parts from radiation protection areas,” which was published in 2009 [14]. Dismantling and disposal should be performed based on the history of an accelerator, operating time, and component materials. In particular, the establishment of a disposal standard for an accelerator is proposed by considering the nuclides of each component. However, as in Korea, no clear procedures and regulations exist, but these will be considered in the next revision of the radiation protection regulations.
In accordance with the treaty (2016/C 203/01) published in 2016 by the European Atomic Energy Community (Euratom), European Union (EU) countries, such as Germany, Sweden, the United Kingdom, and France, have prepared disposal plan reports for when radioactive waste is generated [15]. Each member state must provide the European Committee with a radioactive waste disposal plan and determine whether the implementation of the plan could result in water, soil, or radioactive contamination. The reports must include information about the facility from which the waste originated, the distance to the EU member state closest to the facility, whether the waste is stored prior to transportation, and whether it is within the dose limits [16].
In Canada, to dismantle a facility where a medical linac is used, a permit application is first submitted, as well as a plan of action. As shown in Table 2, a final decommissioning report, including a decommissioning plan, information on generated radioactive materials, preparation for disposal of other hazardous substances, and other factors, should be prepared and submitted to the Canadian Nuclear Safety Commission (CNSC). At this time, Class II equipment is regulated as follows:
Table 2 . Content of final medical linear accelerator dismantling report in Canada.
Outline of the decommissioning plan | Decommissioning schedule |
Manpower qualification and training | Name and title of the person responsible for decommissioning plan |
Estimation of the type, activity, and radiation dose of nuclear materials | The properties, types, and radioactivity of radioactive materials or contamination information of the nuclear facility |
Disposal of Class II regulated equipment, nuclear and hazardous materials | Proposed final disposal method for the major components of the accelerator (e.g., sale or disposal, return to the manufacturer, transfer to another facility for potential reuse, or kept by the license holder for future reuse) |
• Particle accelerators with beam energy of less than 50 MeV that are capable of producing nuclear energy
• Irradiators using nuclear material of 1,015 Bq or higher
• Irradiators requiring shielding because the dose rate at 1 m exceeds 1 cGy/min
• External treatment devices or remote brachytherapy devices (afterloaders) using a radioactive source
1) Disposal method in CanadaCanada disposes of parts differently depending on the level of activation of products from medical linacs and the possession of a CNSC license. In the case of a permitted facility with a CNSC license, the linac is returned to its manufacturer. If the facility has no license, the accelerator or its components are transferred to a repair company. Except for the above examples, waste is typically disposed according to clearance criteria.
Other than for a return to the manufacturer (in the case of a transfer to a repair company) or when using general waste disposal methods, the requirements of section 5.1 of the Nuclear Substances and Radiation Device Regulations must be satisfied [17]. In the absence of a license, a linac can be disposed of if the radioactivity or concentration of radioactive nuclear material does not exceed standard guidelines. In Canada, a dose rate-based measurement method is recommended. In the case of medical accelerators, conditional clearance is allowed if the measurement is less than 0.5 µSv/h when measured at 5 cm from the accessible surface of the component [18].
After disassembly of the linac, the classified radioactive parts must be stored in a storage box that conforms to a certain standard or disposed of after storage. In countries that recommend storage boxes for storing radioactive waste and linac parts, we classified the standards of Japan’s Society Standard Technical Reports and reports from Varian Co., as shown in Table 3 [11]. The basic standard is 50 L in Japan and 210 L in the United States. In Japan, an application is submitted to borrow a waste storage container. A 50 L drum can be borrowed for free and 210 L drums are rented for a fee. At this time, four 50-L drums are typically used. In the United States, 55 gallon (210 L) drums and the insertion of foam are required for the storage and management of radioactive parts. It is recommended that three 5-gallon (19 L) steel drums are used for other parts and that two plastic tarps are used to protect the floor and collect contaminated dust. Wooden pallets can be used if necessary.
Table 3 . Comparison of medical linac radioactive waste storage containers.
Country | Japan | USA |
---|---|---|
Standard | 50 L | 210 L (55 gallons) |
Other information | Fill out the application for borrowing of waste containers | 210 L drum and inserted foam are required as standard for storage and maintenance of radioactive components |
The clearance criteria for radioactive waste from the medical linac and the method of evaluating the activation differ, as shown in Table 4. As a detector for evaluating radioactive waste, Japan, the United States, and Canada typically use a survey meter. The location of the measurement is at a distance of 1 cm in Japan and the United States, but 5 cm in Canada. The clearance criterion is 10 µSv/y in all three countries, which is the same as in Korea. Canada allows a clearance of 0.5 µSv/h or less. This is a calculated value assuming that the annual allowance standard is an average working time of 40 hours and that 15 linac parts are managed per year.
Table 4 . Criteria for evaluation and clearance of radioactive waste in the linac.
Country | Japan | USA | Canada |
---|---|---|---|
Measuring instrument | NaI(Tl) scintillation survey meter | NaI(Tl) scintillation survey meter, Geiger–Muller (GM) counter Counter, etc. | Survey meter |
Measuring location | 1 cm distance | 1 cm distance | 5 cm distance |
Clearance criteria | 10 µSv/y | 10 µSv/y (1 mrem/y) | 0.5 µSv/h (10 µSv/y) |
Other | Calculate the amount of radioactivity (Bq) based on the dose rate (µSv/h) measured (weight measurement and conversion factor applied) | Effective distance of scintillator instrument: 1 cm from the surface | When converting to the effective dose, use the 30 cm standard (distance inverse square law) |
SLAC, Stanford Linear Accelerator Center..
In this study, to establish safety regulation guidelines and procedures for the management of radioactive waste from medical linacs in Korea, the current management practices in Korea and abroad were investigated.
As a result of this investigation, it was shown that standards and procedures for disposing of a linac have yet to be established in Korea. Because activated waste generated by a medical linac is not classified as radioactive waste, the Korean radioactive waste agency, a facility that disposes and manages waste, handles only radioisotopes.
Because no legally prescribed procedure or standard for disposing of a linac exists, it was found that most medical institutions do not have safety management regulations. In addition, radioactive waste is collected by companies without following any procedures or guidelines or the head of medical linacs are stored in the waste storage areas at hospitals. It was shown that the institutions or individual owners in Korea collect the waste by using a company but without any action taken at medical institutions.
Japan, the United States, and Canada have guidelines to treat radioactive waste that is produced by a linac. Japan has regulated radioactive cargo from linacs in the same way that radioactive isotopes are regulated, and the United States and Canada have proposed clearance criteria for radioactive waste. However, most reports from the EU, the International Atomic Energy Agency, and the United States have provided management guidelines for research or large-scale accelerators, but not for linacs.
For the safe management of a medical linac, it is necessary to establish safety management regulations for radioactive waste produced at medical institutions.
First, before dismantling the linac, a dismantling and disposal plan must be prepared and reported to the KINS as recommended by European nations, such as Germany. In addition, medical institutions should form a dedicated team that will perform the work, as is done to Japan. For the process of disposal, as suggested by the processes performed Japan, the United States, and Canada, the dose rate of the components is measured using a survey meter and the general and radioactive waste should be classified according to the 0.5 μSv/h standard. In addition, the sorted parts must be stored or transported in standardized drums 50 or 210 L in size.
In Korea, standards for disposal, such as dose limits, are required for medical linacs. As in other countries, a system for the disposal of a linac according to a clear procedure should be established.
This work was supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) using the financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2003013).
The authors have nothing to disclose.
All relevant data are within the paper and its Supporting Information files.
Conceptualization: Na Hye Kwon, Sang Hyoun Choi. Data curation: Na Hye Kwon. Funding acquisition: Sang Hyoun Choi. Investigation: Jin Sung Kim. Methodology: Kum Bae Kim, Dong Wook Kim. Project administration: Sang Hyoun Choi. Validation: Dong Oh Shin. Visualization: Young Jae Jang. Writing–original draft: Na Hye Kwon. Writing–review & editing: Nahye Kwon, Sang Hyoun Choi.
Table 1 Contents of general program documents and documents related to clearance
General program documentation | Additional documents for clearance |
---|---|
Related regulations and standards | Additional process knowledge used in the measurement process during clearance (beam parameters and operating conditions, materials, etc.) |
Table 2 Content of final medical linear accelerator dismantling report in Canada
Outline of the decommissioning plan | Decommissioning schedule |
Manpower qualification and training | Name and title of the person responsible for decommissioning plan |
Estimation of the type, activity, and radiation dose of nuclear materials | The properties, types, and radioactivity of radioactive materials or contamination information of the nuclear facility |
Disposal of Class II regulated equipment, nuclear and hazardous materials | Proposed final disposal method for the major components of the accelerator (e.g., sale or disposal, return to the manufacturer, transfer to another facility for potential reuse, or kept by the license holder for future reuse) |
Table 3 Comparison of medical linac radioactive waste storage containers
Country | Japan | USA |
---|---|---|
Standard | 50 L | 210 L (55 gallons) |
Other information | Fill out the application for borrowing of waste containers | 210 L drum and inserted foam are required as standard for storage and maintenance of radioactive components |
Table 4 Criteria for evaluation and clearance of radioactive waste in the linac
Country | Japan | USA | Canada |
---|---|---|---|
Measuring instrument | NaI(Tl) scintillation survey meter | NaI(Tl) scintillation survey meter, Geiger–Muller (GM) counter Counter, etc. | Survey meter |
Measuring location | 1 cm distance | 1 cm distance | 5 cm distance |
Clearance criteria | 10 µSv/y | 10 µSv/y (1 mrem/y) | 0.5 µSv/h (10 µSv/y) |
Other | Calculate the amount of radioactivity (Bq) based on the dose rate (µSv/h) measured (weight measurement and conversion factor applied) | Effective distance of scintillator instrument: 1 cm from the surface | When converting to the effective dose, use the 30 cm standard (distance inverse square law) |
SLAC, Stanford Linear Accelerator Center.
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