1. Fire Prevention Measures and Points to Keep in Mind while at a Facility that Handles Radiation in the Event of a Disaster

Transcription

1 RADIATION RE-EDUCATION MATERIALS THE UNIV. OF TOKYO DOC No.35(2017) 1. Fire Prevention Measures and Points to Keep in Mind while at a Facility that Handles Radiation in the Event of a Disaster 2. Guidelines for the Transfer of Ownership of Chemical Substances at The University of Tokyo 3. Basic Concept of Dose and Dose-Rate Effectiveness Factor (DDREF) 4. Safety Mechanism for X-ray Diffractometer 5. Current Regulatory Status on Naturally Occurring Radioactive Material (NORM) 1. Fire Prevention Measures and Points to Keep in Mind while at a Facility that Handles Radiation in the Event of a Disaster This paper explains how to respond to disasters in facilities that handles radiation from the perspective of the fire department. We would be pleased if this article helps to raise your awareness regarding fire and disaster prevention. 1. Introduction A summary of steps to take in the event of a fire and/or leakage accident at a facility handling radioactive materials are given. You must be aware of the following characteristics to respond to this type of disaster. The presence of radioactive substances and radiation cannot be felt by the five senses, and it is necessary to use special measuring instruments for disaster response. Specialized knowledge on radiation etc. is required for disaster response. Employers are obliged to take measures at the time of danger, and have great responsibility for disaster response. The purpose of firefighting activities is to promote early rescue and relief of victims and the prevention of the spreading of substances that lead to pollution while ensuring residents' safety. Therefore, the fire brigade will enter the disaster site, while eliminating exposure, pollution and other risk factors. What is important here is collaboration with facility personnel. Support in the form of advance information, advice for firefighting activities, radiation measurement and use of equipment are indispensable for achieving the purpose. 2. About firefighting activities [1] Protective Equipment We wear protective clothing and respiratory devices to prevent contamination and internal exposure (Left Figure). When responding to a fire, firefighting clothing is worn on top of the protective clothing (Right Figure). These protective equipment do not reduce external radiation exposure. If the protective equipment is contaminated with radioactive material (including suspicion), it will be removed in the decontamination zone (see [3] below) and taken out of use to prevent the spread of contamination. An example of protective equipment [2] Radiation Measuring Instrument Instruments Purposes Unit Picture (For Example) Personal Dosimeter (Pocket Dosimeter) In order to manage activities, you must be aware of the external exposure dose of each person. Sievert: Sv, msv, etc Air Dose Rate Meter Being aware of the intensity of radiation in the activity environment will help in reducing external exposure. Hourly Sievert: msv/h, μsv/h, etc

2 Instruments Purposes Unit Picture (For Example) Measuring instrument for contamination test Surface contamination of the environment, human body, equipment, etc. is measured in order to prevent internal exposure and contamination. Count per Second: cps [3] Defining Areas and Entry Control In addition to preventing exposure and contamination of the work force, strict defining of areas and entry control must be conducted in order to prevent the spread of pollution. The area judged to be dangerous due to the air dose rate condition (0.1 msv / h or more), contamination by radioactive substance, or on the advice of the person concerned with the facility is set as "Radiation Hazardous Area". We will set up a "decontamination zone" to decontaminate victims and work force on the safe side. If existing decontamination facilities and facilities for pollution inspection of the facility can also be used, the decontamination zones will be set to include this. When entering the radiation hazardous area and the decontamination area, we will wear protective equipment appropriate for the situation and carefully monitor radiation exposure. In addition, the site command center (site conducting the operational command or accumulating information on site) and on-site relief center are located in safe places outside the above-mentioned area. An example of the area setting is shown in the following diagrams. The figure on the left shows an example where the entire building is designated as a danger area and the decontamination area is located outdoors. The figure on the right shows an example where the pollution inspection laboratory in the building is set as the decontamination area. Wind Direction Wind Direction On-site Relief Center Place of Disaster On-site Relief Center Place of Disaster Pollution Inspection room Command HQ Command HQ Decontamination Office Pollution inspection center Radiation hazard zone Decontamination area Rescue route [4] Completion of Activity We will finish our activity when all of the following are complete. A) When everyone needing rescue have been rescued and transported to a medical institution. B) When measures to prevent the spread of damage caused by radioactive substances etc. are complete. C) When consultation with operators of business and facilities regarding the treatment of radioactive materials and pollutants left on site has been completed. Hongo Chemical Mobile Company The Hongo Fire Department adjacent to the Hongo Campus of the University of Tokyo has deployed a specialized "chemical mobilized company" to respond to disasters relating to radioactive and chemical substances.

3 3. Collaborating with the fire brigade at times of disaster [1] From calling to the arrival of the fire brigade A) Please make sure that you provide details if radioactive substances are involved, such as "facilities handling radioactive materials are on fire" or "radioactive material is leaking". In response to this, the fire brigade will wear protective equipment from the time they arrive to control exposure to radiation. B) Please specify the location where radiation management staff and other relevant staff who understand the situation will join up with the fire brigade. Please select a safe location that is not affected by radiation exposure or contamination for the meeting place. C) On the arrival of the fire brigade, officials specified in (B) should advise the fire brigade about the safe approach to the disaster site, taking into consideration the risk of exposure to both pollution and radiation. [2] Advice on providing information and other activities Please provide information and advice regarding rescuing and to prevent spread of damage to the person in overall charge as well as the chief of the mobile chemical response unit at the on-site command headquarters. The following table provides some examples. Item Judgement of urgency Condition inside the facility Activity risk Risk of spread of pollution [3] Support for activities Contents of information / advice from relevant staff Presence or absence of those needing to be rescued, number of people, place, etc. Impact of radiation on those needing rescue Access route to the location of disaster (such as provision of drawings) How to enter the facility (such as method for unlocking security doors/gates in controlled areas) Whether there is a decontamination facility and contamination inspection center on-site and whether they can be utilized Location and presence of firefighting equipment Risk related to radioactive material On-site radiation level Presence / absence of contamination (sealed source or unsealed source) Fire, explosion hazard (storage of gases and hazardous materials, etc.) Risk of toxic substances, etc. Risk of high temperature, electricity, etc. Danger such as falling, pinching Risk of contamination spread determined from disaster situation and measured value Presence or absence of devices that will be an obstacle (negative pressure air conditioning etc.) and possibility of its use Presence or absence of drainage equipment (for collecting contaminated water) Use of information and advice in firefighting activities Determining policy for activity Request of support from firefighters Decision of entry method Determining area setting Setting up of decontamination area, and determining appropriate method of decontamination Decision on extinguishing method Selection of protective equipment Decision on how to enter Safety management during activity Understanding risk involved when hosing with water Decision area setting Decision on extinguishing method A) In order to support the activities of the fire brigade and to ensure the safety of the surrounding residents, we may ask for cooperation in taking radiation measurements. Due to the limit in the number and types of measuring instruments deployed in fire brigade, please allow measuring instruments of university to be gather and used for environmental monitoring.

4 B) Please provide support and advice on effective extinguishing such as the operation of on-site fire extinguishing equipment. C) We may ask for support in inspection for contamination and the decontamination of victims and firefighters. Please take into consideration the use of on-site decontamination facility and measuring equipment necessary for that purpose. Also, please try to prevent the spread of pollution, such as removing clothing and footwear from contaminated victims until the arrival of the fire brigade. D) In order to set up the decontamination facility or field relief center, a different building from the disaster location or another level in the same building may be selected, in which case we will ask for cooperation by making the facility available. E) On transferring the affected persons to a medical institution, we may ask for an expert who can explain the situation of exposure to the destination medical institution to accompany them. University staff who cooperate in firefighting activities will assist taking safety measures equivalent to those of firefighters, such as use of protective equipment and management of activities. [4] Usual preparation A) In cooperation with the Hongo Fire Department, please make the appropriate report on the situation concerning storage and handling of radioactive materials, as well as making sure that the staff responsible is properly aware of the situation regarding the storage and handling of radioactive materials, so that appropriate information can be provided in the event of a disaster. B) Please carry out independent fire drills and disaster prevention drills so you are able to minimize the damage in the event of a disaster occurring. C) In order to prevent damage from spreading when a disaster occurs, please manage the handling of goods appropriately and to prevent tipping, falling, and shifting of storage cabinets, etc. D) It is essential for the fire department and the University of Tokyo regularly cooperate to ensure effective firefighting activities. We can strengthen our partnership by regularly implementing security inspection visits (inspection and understanding the conditions of buildings and facilities, as well as the surroundings) with the Hongo Fire department, neighborhood offices, and other fire and police departments as well as taking part in joint firefighting trainings. 4. In conclusion Traffic accidents involving the transport vehicles and fires at facilities have occurred in the past as examples of disasters relating to radioactive materials. There were instances where the fire department responded without knowing that radioactive substances were involved, and cases where staff could not properly explain what was involved when the fire brigade arrived, as a result we, the fire brigade experienced unnecessary exposure as well as working for long periods under such conditions. In order to prevent these from happening, it is important that you properly manage and handle radioactive substances at all times, and that the University of Tokyo and the fire department build a good working relationship. We ask that you raise the awareness about fire and disaster prevention among all the people concerned so that these types of disasters that cause great unease in the community do not occur. Tokyo Fire Department Hongo Fire Station Fire Suppression Section Fire service command Kohji Ono Re-education theme:topix

5 2. Guidelines for the Transfer of Ownership of Chemical Substances at The University of Tokyo There is a large number of diverse chemical substances and equipment as well as waste liquid and waste substances (hereinafter referred to as chemical substances etc.) inside many laboratories. These chemical substances etc. undergo certain processes when brought into the lab, and are kept in an appropriate manner. However, the environment surrounding the use of such chemical substances changes daily. Over time laws concerning the management of said chemical substances etc. may be revised requiring additional paperwork to be processed. New management standards may be implemented. Sometimes the use of certain chemical substances etc. may even be prohibited by law. Generally, the university is capable of taking measures on the chemical substances etc. under its management even in the event of sudden changes in the law. However, there have been cases of chemical substances etc. not being disposed of or transfer of ownership not being properly conducted in the event of a laboratory closing down. There have also been cases where some chemical substances etc. were forgotten and at a later date found to be below legal standards. These problems occur relatively frequently and in both small and large scales. There have even been cases reported where radioactive materials have found in piping spaces that were being used for storage, or small refrigerators containing radioactive isotopes (RI) set up in shared corridors without permit or identification of the owner. The university has special guidelines for the transfer of ownership of chemical substances etc. in place to prevent these types of problems from occurring. The full text of the guidelines is available in the link given at the end of this document. Key points from the guidelines are laid out below, and we would like to request you to keep them in mind as important aspects of the management of laboratories. Guidelines for the transfer of ownership of chemical substances This guideline contains conducts that must be observed, when chemical substances etc. are brought into the university, when new academic and administrative staff are hired or when ownership of the chemical substances etc. are transferred in the event of retirement of existing academic and administrative staff (including hand-over of responsibilities of laboratories). As a rule, whenever a staff in charge of a laboratory retires, all chemical substances etc. under their management should be disposed of, and only under special circumstances should ownership be transferred to another staff. In such an event the items specified below must be followed. If there are no other staff to take over the ownership, then the retiring staff must take responsibility for the disposal of the chemical substances etc. (1) Conditions for transferring ownership of chemical substances etc. Academic and administrative staff are able to transfer ownership of chemical substances etc. to other staff members by observing the following points. (a) Produce a certificate for transfer of ownership of chemical substances etc. (b) Inform in writing the Environment, Health and Safety Office of the faculty/graduate school/institute that the laboratory receiving and handing over belongs to in advance of the transfer of ownership. (c) Confirm the actual hand over of the chemical substances etc. and the certificate for transfer of ownership in the presence of a member from the Environment, Health and Safety Office. (d) Have the Environment, Health and Safety Office confirm that the receiving academic and administrative staff possess the necessary qualifications to receive and store the chemical substances etc. (2) Conditions for bringing in chemical substances etc. Academic and administrative staff are able to bring in chemical substances etc. at the time of their employment to the university by observing the following points. (a) Produce a certificate of possession for the chemical substances etc. being brought in. (b) Confirm the actual state of the chemical substances etc. and the certification in the presence of a member from the Environment, Health and Safety Office of the faculty/graduate school/institute that the staff is affiliated with. (c) Have the Environment, Health and Safety Office confirm that the relevant laboratory possesses the necessary equipment and qualifications etc. to receive and store the chemical substances etc. (3) Store the certificates

6 Link to the full text of the Guidelines for the Transfer of Ownership of Chemical Substances %83%E5%AE%89%E5%85%A8%EF%BC%89 [ 環境安全本部通達一覧 _ 平成 27 年度 _ 番号 :H ] (List of Notifications from the Division of Environment, Health and Safety: AY2015 Ref. No.: H ) Division for Environment, Health and Safety Hirotomo Shimizu, Yusuke Seki Re-education theme:laws and Management

7 3. Basic Concept of Dose and Dose-Rate Effectiveness Factor (DDREF) The biological effects of radiation depend on total dose and dose rate. In general, the amount and duration of radiation exposure affects the severity or type of health effect. There are two broad categories of health effects: acute (short-term) and chronic (long-term). Examples include accidentally handling a strong industrial radiation source or extreme events like nuclear explosions. Chronic exposure, on the other hand, is low levels of exposure over a long period of time (low dose rate: < 0.1 mgy / min averaged over 1 hour, low dose: < 100 mgy, UNSCEAR 2012). Examples could be exposure from high levels of radon in a basement or occupational one among hospital workers. A large dose given in a short amount of time is more damaging than the same dose given over a longer period of time. Chronic radiation exposure, at low levels, presents a much reduced health risk, as it is of low quantities over long periods of time, allowing the body to repair any damage made to the cells. A linear no-threshold relationship (LNT model) was adopted by the radiation protection community many years ago. At low doses and low dose rates, the actual risk is overestimated by a certain factor if the risk values of high doses and high dose rates are extrapolated in linear fashion to low doses and low dose rates. The International Commission on Radiological Protection (ICRP) therefore adopted a dose and dose-rate effectiveness factor (DDREF) to adjust for this perceived overrepresentation. Risk values largely determined using epidemiological studies on the survivors of the Hiroshima and Nagasaki atomic bombings are divided by this DDREF for low-dose and low-dose-rate radiation protection applications. Risks for low doses and low dose rates = Risks for high-dose and low-dose-rate DDREF Figure 1. Risk values of low-doses and low-dose rates. The linear-quadratic (LQ) equation (E = αd + βd 2, where D is the dose) is well accepted in the field of radiological sciences as a mechanistic model of radiation action. The equation is composed of two terms: linear term and the quadratic term. Theoretically, the α term represents the single-hit intratrack component, and β represents the two-hit intertrack component. The LQ equation assumes that while the linear term is independent of dose rate, the quadratic term is dose rate sensitive. So, the dose response of a biological effect for low-dose-rate exposures (EL) can be described as below. Figure 2. Schematic curves of incidence versus absorbed dose. (NCRP Report No. 64,1980) EL = αd The DDREF is estimated by comparing the linear extrapolation (curve B) of the induced incidence for a set of acute dose points (curve A) with the linear curve (D) for low dose rate. The DDREF is equal to the slope αl for curve B divided by the slope α1 for curve D which indicates the essentially linear proportion of curve A at low doses (Figure 2). DDREF = E/EL = 1 + (β/α)d ICRP selected 2 as the most reasonable value for DDREF in Numerical values on a potential reduction factor, i.e., values between 2 and 20, were also suggested by UNSCEAR and other organizations which reviewed data obtained from cellular and animal experiments (Table 1). In the

8 latest recommendations by ICRP (2007), a value of 2 was selected again, a value that was thought to be supported by the fact that this was the value of the mean of the probabilistic uncertainty distribution for DDREF suggested by a number of committees. On the other hand, recent studies indicate that several factors may affect the theoretical dose-response relationships described above: induction of an adaptive response to an initial exposure, which can reduce the effect of later exposures; a bystander effect that causes an irradiated cell to have an effect on a nearby unirradiated cell. There is a general assumption that the LQ model is appropriate for the derivation of a value of DDREF. Based on current scientific findings, an international reconsideration including adjustment or abolishment seems to be urgently necessary for application of DDREF. Table 1. DDREF value proposed by several organizations. Organization Year DDREF UNSCREAR ICRP USNAS Reference [1] International Commission on Radiological Protection (ICRP) Pub [2] United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) [3] United States National Academy of Science, BEIR VII [4] Strahlenschutzkommission (SSK), Dose and dose-rate effectiveness factor (DDREF) Faculty of Medicine Center for Disease Biology and Integrative Medicine Atsushi Enomoto Re-education theme:human Body Effects

9 4. Safety Mechanism for X-ray Diffractometer 1. Introduction In X-ray diffractometer, the safety mechanism design complies with three fundamental principles (Justification, Optimization and Dose limitation) published by ICRP (the International Commission on Radiological Protection) and employs the fundamental (ALARA principle), in which all exposures are as low as reasonably achievable for users while considering individual exposure or the number of people exposed by economic and societal factors. 2. Safety mechanism for X-ray diffractometer This chapter introduces safety mechanism of one of the X-ray diffractometer systems. For example, the control software (SmartLab Guidance) of SmartLab will place guidance operations, such as arranging / integrating optics, aligning sample position, and measuring sample according to the application. By choosing application, even user of novice can perform just like an expert to align optics, and measure sample under equivalent condition. Therefore, without opening X-ray enclosure, optics alignment is able to perform, so that there is no risk of X-ray exposure. (Under line indicates the features of the latest equipment) X-ray protecting structure and safety mechanism are described as below X-ray enclosure (1) X-ray warning lamp (Yellow) X-ray enclosure has a Yellow LED on the top, of which ON represents X-ray generating. (2) X-ray enclosure (Side cover) X-ray enclosure covers optics, like goniometer. (3) X-ray enclosure front doors (Interlock) Front door panel features lock mechanism. While DOOR button (Yellow) is off, the doors are locked and X-ray enclosure is not opened. (4) DOOR button Push the button to open the doors of X-ray enclosure. (5) HV ENABLE key Rotate the key to clockwise to release the system lock, which allows user to operate POWER ON. (1) X-ray warning lamp Detecting disconnection or short circuit makes X-ray HV off and avoids generating X-rays. (2) X-ray enclosure (Side cover) Side cover puts on iron plate as 9mm thickness equivalent at the direct beam direction to block exposure. (3) X-ray enclosure front doors (Interlock) Interlock system consists of double switches (contact points) to prevent malfunctions from single fail cause. The safety system design avoids X-rays exposure caused by mis-handling or mis-operation. While radiating X-rays, the doors are locked and X-ray enclosure is not opened. If the system does not sense the correct doors lock, X-ray HV is shut off, and X-rays is not able to generate. (4) DOOR button While X-ray shutter is OPEN, pushing DOOR button makes shutter off and allows the system to open the door. When the system allows opening the doors, the system brinks Yellow LED DOOR button, and beeps to notify the status to release the doors lock. Push the DOOR button, and open the X-ray enclosure under the status, which allows you to open the doors, while X-ray shutter is closed, so X-rays stop irradiating. (5) HV ENABLE key Without HV ENABLE key, X-rays are not generated. While system is off, the key is removable. So that system manager can manage/storage the key.

10 (6) X-ray leakage The radiation leakage level (1cm equivalent dose rate) does not exceed 0.1μSv/h around the main parts of equipment external cover. Outside the equipment, there is no "area to exceed 1.3mSv for 3 months", which is defined as radiation controlled area by Radiation Hazard Prevention Act X-ray tube (sealed-off X-ray tube) (1) X-ray shutter alarm lump (Red) X-ray shutter red LED ON represents X-ray shutter "OPEN" operation. (2)X-ray shutter Shutter shield part consists of 3mm or more thickness heavy metal. (3)X-ray tube (Tube sealed) The outer X-ray tube is made of heavy metal, aperture area and internal are shield by lead plate. (1) X-ray shutter alarm lump Detecting disconnection or short circuit makes X-ray HV off and avoids generating X-rays. (2) X-ray shutter X-ray shutter unit consists of two sensors, OPEN and CLOSE, and shutter Safety circuit is always monitoring the signals of two sensors, OPEN and CLOSE. The safety circuit design avoids X-ray exposure caused by mis-handling or mis-operation. X-ray shutter is not opened while X-ray enclosure is not closed. X-ray is not generated because X-ray HV power is shutdown when the system has a positioning error with X-ray shutter shield part, or whichever OPEN sensor or CLOSE sensor is broken. (3) X-ray tube (Tube sealed) The radiation leakage level (1cm equivalent dose rate) does not exceed 0.1μSv/h around the main parts of equipment external cover. 3. Handling precautions Please remind yourself on the following precautions as your reference when you are operating the system safely. Wear the radiation dosimeter with your body as regulated position during equipment operation. Accompany with equipment manager when you replace the X-ray generator unit. Place the periodical system check and measure the X-rays leakage. Record the system operation, time, user name, and if any problems. Place the periodical radiation safety training and medical health check. 4. Summary The recent X-ray diffractometer equips higher reliable safety electric circuit, which features double check monitoring function, to prevent from mis-handling or mis-operation under malfunction with single error reason. With X-ray diffractometer, the operation is required to meet the national and local government regulation. Please comply with these regulations to ensure work, operations, management under the safety manner. X-ray instrument division, Rigaku Corp. Re-education theme:x-rays

11 5. Current Regulatory Status on Naturally Occurring Radioactive Material (NORM) 1. What is a Naturally Occurring Radioactive Material (NORM)? Radioactive nuclides are classified as "artificial" (artificial radioactive nuclides) and "natural origin" (naturally occurring radioactive nuclides such as U-238 series and Th-232 series). A material that includes artificial radioactive nuclides is referred as "artificial radioactive material." A material that includes naturally occurring radioactive nuclides is referred as "Naturally Occurring Radioactive Material (NORM)". <U-238 series> U-238, Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210, Pb-206 (stable) <Th-232series> Th-232, Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212, Pb-208 (stable) Immediately after Earth was born, there were many types of naturally occurring radioactive nuclides on the earth. These radionuclides repeat the radioactive decay by releasing radiation before finally change into stable nuclides that do not release radiation. However, the speed of decay for each radionuclide differs, and some radionuclides that decay slowly still remain even now, 4.6 billion years after the Earth was born. Therefore, all natural resources such as soil, rock, ore, coal, and petroleum include naturally occurring radioactive nuclides. Their levels depend on areas or materials. Figure 1. Status of naturally occurring radioactive nuclides on the Earth formation period and today 2. Current states and issue Activity concentrations of NORMs have not yet been well-identified because the activity concentrations in NORMs vary over a wide range, starting at very low levels. If these are high concentrations, the workers who handle the material can be unknowingly exposed to radiation at a high level. Moreover, the workers could be exposed to radiation with a high level when handling products, by-products, or waste containing highly concentrated naturally occurring radioactive nuclides. On this basis, the International Commission on Radiological Protection (ICRP) suggested that exposure to NORM for industrial use should be controlled as occupational exposure. NORMs do not leak high amounts of radiation and create casualties that result in acute disorders of the human body. However, the future risk of cancer or genetic disorder would be slightly increased. 3. Japanese Laws concerning NORM If ore, rock, or building materials include higher concentration levels of radioactivity than those permitted by "Nuclear Reactor Regulation Law", the material is subjected to regulation (the Ministry of Education Culture, Sports, Science and Technology (MEXT) notification is required) (Table 1). Table 1. Nuclear Reactor Regulation Law Materials requiring notification Uranium or thorium exceeding the following predetermined levels: Activity concentration: 74Bq/g (solid condition: 370Bq/g) Quantity: Quantity of uranium x 3 + quantity of thorium >= 900g Materials requiring Permission Natural uranium, depleted uranium, and uranium compounds with the total amount exceeding 300 g Enriched uranium of any type Thorium and thorium compounds with the total amount exceeding 900g

12 Considering the risk of exposure of workers handling NORMs, NORMs should be controlled by appropriate standards. A "Guidelines on the Security for Materials and Products Including Uranium or Thorium" publication was officially announced by the MEXT on June 26, These guidelines provide basic advice for manufacturers and workers (not regulation laws). In these guidelines, monazite, bastnaesite, zircon, tantalite, phosphorus ore, titanium ore, coal, purified uranium, and purified thorium are designated as materials for these guidelines. Concentration of uranium or thorium exceeding 1 Bq/g is covered in these guidelines. These guidelines are to be revised on an ongoing basis according to the actual status of measures implemented at each factory. On the basis of the new regulation policy on NORM developed by the International Atomic Energy Agency (IAEA) in 2014 [IAEA GSR Part 3, 2014], it is important to consider materials that have not been focused until now. 4. Activity concentration of NORMs Investigations of activity concentrations in NORMs has been performed (Table 2). The database on these investigations was developed by National Institutes for Quantum and Radiological Sciences and Technology and can be freely accessed on the internet (website: (Figure 2). Table 2. Activity concentration in NORMs Material U-238 series (Bq/g) Th-232 series( Bq/g) Monazite Coal Ilmenite Titanium ore Typical soil Reference [1] NORM database, National Institutes for Quantum and Radiological Sciences and Technology, Figure 2. NORM database [2] UNSCEAR, Sources and effects of ionizing radiation. UNSCEAR 2000 report. UNSCEAR, New York [3] IAEA, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. GSR Part3. IAEA, Vienna Hirosaki University Institute of Radiation Emergency Medicine Kazuki Iwaoka Re-education theme:nuclear Source Materials / Nuclear Fuel Materials