Radiation Doses Of Workers Research Articles

Theoretical model for calculating and adjusting radon activity concentration in ventilation networks of uranium mines considering pressure drop effect

The radiation dose of workers in underground uranium mines mainly comes from radon and radon progeny. To ensure a healthy and safe work environment, it is necessary and urgent to optimize the design of ventilation systems. As such, based on the simplified radon diffusion-advection migration model of the rocks, this paper proposes 1) two methods for determining the radon exhalation rate modified by pressure drop, 2) three methods for calculating radon activity concentration of single-branch, and 3) the novel adjustment algorithm and solving procedures for calculating and adjusting the radon activity concentration in ventilation networks by modifying the radon exhalation rate, demonstrated on a specific ventilation network in a simulated underground uranium mine with calculation and analysis via MATLAB. The results show that 1) the radon exhalation rate of different branches can be modified by their pressure drop, and 2) the proposed method can be used to reveal the influences of different ventilation methods and fan pressures on the radon activity concentration in the ventilation network and the radon release rate to the atmosphere.

Radiation Exposure Characteristics among Healthcare Workers: Before and After Japan's Ordinance Revision.

Radioactive materials and ionizing radiation have both medical value and disease risks, necessitating radiation dose measurement and risk reduction strategies. The International Commission on Radiological Protection (ICRP) lowered the lens of the eye exposure limit, leading to Japan's revised "Ionizing Radiation Ordinance." However, the effects on radiation exposure in medical settings and compliance feasibility remain unclear. To examine the impact of the revision to the "Ionizing Radiation Ordinance" and use it for measures to reduce exposure to radiation, a comprehensive analysis was conducted on data collected from Nagasaki University Hospital, Hiroshima University Hospital, and Fukushima Medical University Hospital in 2018, 2020, and April to September 2021. This included information on age, sex, occupation, department, and monthly radiation doses of workers, aiming to assess the impact of the revision to the "Ionizing Radiation Ordinance" on radiation exposure before and after its enforcement. Out of 9,076 cases studied, 7,963 (87.7%) had radiation doses below the measurable limit throughout the year. Only 292 cases (3.2%) exceeded 1 mSv y -1 , with 9 doctors and 2 radiological technologists surpassing 5 mSv y -1 . Radiological technologists showed significantly higher doses compared to doctors, dentists, and nurses (p < 0.01), while male subjects had significantly higher exposure doses than females (p < 0.01). No significant changes in radiation exposure were observed before and after the revision of the Ionizing Radiation Ordinance; however, variations in radiation exposure control were noted, particularly among nurses and radiological technologists, suggesting the impact of the revision and the need for tailored countermeasures to reduce radiation dose in each group.

Radiation dose in radiologist from cerebral angiography using optically stimulated luminescence dosimeter

Background: The number of cerebral angiography procedures is increasing, resulting in higher X-ray radiation doses received by radiologists. Consequently, understanding the radiation doses received by radiologists and the accumulation of radiation in control rooms is crucial for guiding prevention strategies against radiation hazards. Objectives: This study aimed to measure and evaluate radiation doses to the hands, lenses of the eyes, and thyroids of radiologists performing cerebral angiography procedures, as well as to measure the accumulated radiation dose in the control room. Materials and methods: OSL dosimeters were placed on the eyeglass frames, thyroids, hands, and legs of radiologists performing 20 cerebral angiography procedures, as well as on the wall and window of the control room. Results: Radiologists’ average radiation doses were measured at specific body parts as follows: left eye (49 µSv), right eye (15 µSv), left hands (34 µSv), right hands (16 µSv), left legs (27 µSv), right legs (7 µSv), and thyroid glands (14 µSv). Notably, the received doses remained well within the maximum radiation dose limit established by the International Commission on Radiological Protection (ICRP). When calculating the maximum number of procedures that can be performed annually, we based it on the limit of the radiation dose that the eyes’ lenses should not exceed. Our findings revealed that the permissible number of procedures determined by the lens radiation dose limit, should not surpass 405 cases annually (equivalent to 34 cases per month). The radiation dose from therapeutic angiography procedures was discovered to be up to 5 times higher than that from diagnostic angiography procedures. The maximum accumulated radiation dose in the control room was 1.18 µSv/hr, which remained below the limit of the Department of Medical Sciences (&lt; 3 µSv/hr). Conclusion: Radiologists receive less radiation from cerebral diagnostic angiography than therapeutic angiography. Organs on the left side were exposed to greater radiation levels than those on the right side. Wearing radiation protection devices during each procedure can reduce radiation exposure and mitigate long-term effects on radiologists. It is recommended to monitor and calculate the accumulated radiation dose of workers to ensure their exposure remains within safety limits.

A report on a survey among Portuguese Association of Interventional Cardiology associates regarding ionizing radiation protection practices in national interventional cath-labs

Introduction and objectivesConcerns surrounding the consequences of ionizing radiation (IR) have increased in interventional cardiology (IC). Despite this, the ever-growing complexity of diseases as well as procedures can lead to greater exposure to radiation. The aim of this survey, led by Portuguese Association of Interventional Cardiology (APIC), was to evaluate the level of awareness and current practices on IR protection among its members. MethodsAn online survey was emailed to all APIC members, between August and November 2021. The questionnaire consisted of 50 questions focusing on knowledge and measures of IR protection in the catheterization laboratory. Results were analyzed using descriptive statistics. ResultsFrom a response rate of 46.9%, the study obtained a total sample of 159 responses (156 selected for analysis). Most survey respondents (66.0%) were unaware of the radiation exposure category, and only 60.4% reported systematically using a dosimeter. A large majority (90.4%) employed techniques to minimize exposure to radiation. All participants used personal protective equipment, despite eyewear protection only being used frequently by 49.2% of main operators. Ceiling suspended shields and table protectors were often used. Only two-thirds were familiar with the legally established limit on radiation doses for workers or the dose that should trigger patient follow-up. Most of the survey respondents had a non-certified training in IR procedures and only 32.0% had attended their yearly occupational health consultation. ConclusionsSafety methods and protective equipment are largely adopted among interventional cardiologists, who have shown some IR awareness. Despite this, there is room for improvement, especially concerning the use of eyewear protection, monitoring, and certification.

Occupational radiation exposure dose and associated factors among radiology personnel in Eastern Amhara, Ethiopia.

Ionizing radiation is being used more frequently in medicine, which has been linked to recognized biological effects such as cancer and mortality. Radiology services are becoming more widely available in Ethiopian health facilities but there is no compiled record of worker's radiation dose. So, assessing the magnitude and identifying the associated factors of occupational radiation exposure dose among radiology personnel help to design strategies for radiation protection. The study was designed to assess the occupational radiation exposure dose and associated factors among radiology personnel in eastern Amhara, northeast Ethiopia, 2021. Cross-sectional study was conducted from March 25 to April 30, 2021, in 57 health institutions among 198 radiology personnel. The study comprised all eligible radiology personnel. The data were collected using an electronic-based (Google form) self-administered questionnaire, and document review. The data were entered into an excel spread sheet and then, exported to Stata 14 software. Linear regression model was used to analyse the data after checking its assumptions. Variables with a p-value < 0.25 were entered into a multiple linear regression analysis, and those with a p-value < 0.05 were judged significant. VIF was used to check for multi-collinearity. Coefficient of determination was used to check the model fitness. The mean (± SD) annual shallow and deep dose equivalents of radiology personnel were 1.20 (± 0.75) and 1.02 (± 0.70) mSv, respectively. Body mass index (β = 0.104, 95% CI: 0.07, 0.14), practice of timing (β = -0.43, 95% CI: -0.73, -0.13), working experience (β = -0.04, 95% CI: -0.048, -0.032), and practice of distancing (β = -0.26, 95% CI: -0.49, -0.17) were found to be statistically significant factors of annual deep dose equivalent. In addition, body mass index (β = 0.113, 95% CI: 0.08, 0.15), practice of timing (β = -0.62 95% CI: -0.93, -0.31) and, working experience (β = -0.044, 95% CI: -0.053, -0.036 had statistically significant associations with annual shallow dose equivalent. The annual dose equivalents were two times higher than the global average of annual per caput effective dose due to medical exposure. Body mass index, practice of timing, working experience, and practice of distancing were factors of occupational radiation exposure dose. Strategies focusing on increasing the skill, experience, and lifestyle of radiology personnel would be supreme important means to reduce occupational radiation exposure dose.

Assessment of Radiation Exposure Dose for Nuclear Medicine Workers from 18F-FDG, 99mTc MDP, and 99mTc.

Nuclear medicine or diagnostic radiology personnel are always exposed to low-level radiation from radionuclides used in medical diagnostics, which lead to potential biological hazards or effects. External exposure for workers in two nuclear medicine centers was measured by recruiting 120 patients. Three nuclear medicine examinations were performed using F18-FDG PET/CT,99mTc- MDP bones scan, and 99mTc thyroid scan by a digital radiation dosimeter. The average received accumulative radiation dose for workers was found to be 0.838±0.17, 0.527±0.11, and 0.270±0.05 µSv for F18-FDG PET/CT, 99mTc-MDP bones scan, and 99mTc thyroid scan, respectively. The annual effective dose for workers was estimated to be 2.09±0.42, 1.34±0.27, and 0.68±0.14 mSv, respectively. Moreover, the average patient-to-staff dose coefficients were found to be 0.024±0.005, 0.003±0.001, and 0.007±0.002 µSv m2/MBq h for F18- FDG PET/CT, 99mTc-MDP bones scan, and 99mTc thyroid scan, respectively. It is clear from the results that the radiation doses received by workers during the nuclear medicine imaging examinations were less than the doses recommended by the International Commission on Radiological Protection (ICRP) for such examinations.

Radiation Protection in Interventional Radiology/Cardiology-Is State-of-the-Art Equipment Used?

Interventional radiology/cardiology is one of the fields with the highest radiation doses for workers. For this reason, the International Commission on Radiological Protection (ICRP) published new recommendations in 2018 to shield staff from radiation. This study sets out to establish the extent to which these recommendations are observed in Germany. For the study, areas were selected which are known to have relatively high radiation exposure along with good conditions for radiological protection—interventional cardiology, radiology and vascular surgery. The study was advertised with the aid of an information flyer which was distributed via organisations including the German Cardiac Society (Deutsche Gesellschaft für Kardiologie- Herz- und Kreislaufforschung e. V.). Everyone who participated in our study received a questionnaire to record their occupational medical history, dosimetry, working practices, existing interventional installations and personal protective equipment. The results were compared with international recommendations, especially those of the ICRP, based on state-of-the-art equipment. A total of 104 respondents from eight German clinics took part in the survey. Four participants had been medically diagnosed with cataracts. None of the participants had previously worn an additional dosimeter over their apron to determine partial-body doses. The interventional installations recommended by the ICRP have not been fitted in all examination rooms and, where they have been put in place, they are not always used consistently. Just 31 participants (36.6%) stated that they “always” wore protective lead glasses or a visor. This study revealed considerable deficits in radiological protection—especially in connection with shielding measures and dosimetric practices pertaining to the head and neck—during a range of interventions. Examination rooms without the recommended interventional installations should be upgraded in the future. According to the principle of dose minimization, there is considerable potential for improving radiation protection. Temporary measurements should be taken over the apron to determine the organ-specific equivalent dose to the lens of the eye and the head.

Estimation of the historical radiation dose of Korean radiation workers, 1961–1983

Accurate dosimetry plays a key role in evaluating the radiation-induced health risks of radiation workers. The National Dose Registry in Korea contains the dose records of radiation workers in nuclear-related occupations since 1984. Thus, radiation doses for workers before 1984 are often sparse or missing. This study aimed to estimate the historical radiation dose before 1984 for radiation workers in Korea based on dose reconstruction models. The dose reconstruction models were derived from the nationwide self-administered questionnaire survey and the personal badge doses for workers in the cohort of the Korean Radiation Worker Study. The mean estimated annual doses between 1984 and 2016 from the dose reconstruction model were 4.67–0.6 mSv, which closely matched the reported doses of 4.51–0.43 mSv. The mean estimated annual doses between 1961 and 1983 based on the exposure scenarios developed by factors associated with radiation doses ranged from 11.08 to 4.82 mSv. The mean estimated annual doses of individuals in the cohort from 1961 to 1983 ranged from 11.15 to 4.88 mSv. Although caution needs to be exercised in the interpretation of these estimations due to uncertainty owed to the nature of extrapolation beyond the range of observed data, this study offers a sense of the radiation doses for workers during Korea’s early period of radiation-related activities, which can be a useful piece of information for radiation-induced health risk assessments.

"Subacute" course of chronic radiation syndrome

Introduction. The use of ionizing radiation as a production factor in the late 1940s - early 1950s. began in the absence of a clear understanding of the permissible radiation doses for workers, as well as knowledge of diagnostic criteria and developed therapeutic measures for developing chronic radiation sickness (CRS). Since then, a great deal of experience has been accumulated in the diagnosis and treatment of CRS. Currently, there are no conditions at the workplace for chronic exposure of workers in doses exceeding the permissible ones. However, taking into account the constant expansion of the scope of using sources of ionizing radiation, it is necessary to remember about the possibility of CRS development due to prolonged exposure in case of violation of their storage or their loss. The study aimed to explore the formation of radiation bone marrow syndrome (RBS) due to chronic exposure in doses that exceed the maximum permissible, accumulated with different dose rates of radiation. Material and methods. We selected the medical records of 27 people (24 men and 3 women) who had RBS as a result of chronic professional gamma radiation exposure. The selection criteria were the diagnosis of grade II-III chronic radiation syndrome (CRS) in the presence of agranulocytosis or anemic syndrome in the period of the disease formation and, especially, in the development of myelodysplastic syndrome (MDS) or aplastic anemia in the period of the CRS consequences. Identified clinical and dosimetric CRS features of 27 patients exposed to chronic irradiation with a dose rate of 0.0002-0,009 Gy/h and the summary dose of 1.7 and 9.6 Gy, accumulated over a period of 6 to 96 months were compared the characteristics of 84 patients CRS exposed a lower dose rates (less than 0,0003 Gy/h) and 26 patients with acute radiation syndrome moderate (II) severity as a result of irradiation the dose rates of 0.14-3,7 Gy/h, total dose of 2 to 4 Gy. Results. The criteria of atypical subacute CRS course are identified: the rate of chronic radiation exposure - not less than 0.001-0.009 Gy/h with a summary dose of 1.7-9.6 Gy accumulated over a period of 6-96 months, the presence of agranulocytosis in the period of CRS formation and anemic syndrome in the periods of CRS formation and outcomes. These signs predict the development MDS in 60% of the patients in the period of the CRS consequences. Conclusion. Retrospective study determined that long-term human exposure to a dose rate of 0.001-0,009 Gy/h (0,005-0,05 Gy/day) and more in the accumulation of a summary dose of 1.7 and 9.6 Gy and duration of contact 6-96 months in 60% of cases can be expected development CRS with a subacute clinical course RBS. The main factor determining this feature of the course of RBS is the dose rate exceeding 0.001 Gy / h (2 Gy/year). In the subacute course of CRS, the early outcome in MDS is essentially deterministic. The development of agranulocytosis and anemic syndrome are typical signs of the subacute course of CRS.

Occupational radiation dose for medical workers at the University Hospital Center “Mother Theresa” in Tirana

The exposure to environmental and “artificial” radiation sources was investigated in the University Hospital Center “Mother Theresa” in Tirana. The concentration of indoor radon exceeds the reference level of 300 Bq m−3 in some 50% of workplaces, accounting for an average effective dose rate of 3.7 mSv y−1. The average dose rate due to external gamma radiation was measured to be 0.12 mSv y−1. While, the occupational exposure of medical workers was found to be 0.67 mSv y−1 on average. The high radon concentrations account for approximately 83% of worker radiation dose, indicating the need for adopting mitigation actions.

Internal Dose Assessment of Worker by Radioactive Aerosol Generated During Mechanical Cutting of Radioactive Concrete

Removing radioactive concrete is crucial in the decommissioning of nuclear power plants. However, this process generates radioactive aerosols, exposing workers to radiation. Although large amounts of radioactive concrete are generated during decommissioning, studies on the internal exposure of workers to radioactive aerosols generated from the cutting of radioactive concrete are very limited. In this study, therefore, we calculate the internal radiation doses of workers exposed to radioactive aerosols during activities such as drilling and cutting of radioactive concrete, using previous research data. The electrical-mobility-equivalent diameter measured in a previous study was converted to aerodynamic diameter using the Newton–Raphson method. Furthermore, the specific activity of each nuclide in radioactive concrete 10 years after nuclear power plants are shut down was calculated using the ORIGEN code. Eventually, we calculated the committed effective dose for each nuclide using the IMBA software. The maximum effective dose of 152Eu constituted 83.09% of the total dose; moreover, the five highest-ranked elements (152Eu, 154Eu, 60Co, 239Pu, 55Fe) constituted 99.63%. Therefore, we postulate that these major elements could be measured first for rapid radiation exposure management of workers involved in decommissioning of nuclear power plants, even if all radioactive elements in concrete are not considered.

Monitoring of Tritium Internal Exposure Doses of Heavy-Water Reactor Workers in Third Qinshan Nuclear Power Plant

To analyze the tritium internal exposure dose of workers in the Third Qinshan Nuclear Power Plant over the past 15 years. Urine samples provided by workers are tested directly to analyze the tritium concentrations and estimate internal exposure dose. Since 2004, an average of approximately 1600 workers have been monitored annually, with an average annual monitoring frequency of approximately 11 000. Since 2004, the average annual collective dose of tritium internal exposure was 149.62 person·mSv, accounting for 19.07% of the total annual collective dose. A total of 18 workers’ annual individual internal tritium radiation doses exceeded 2 mSv, of which 5 workers’ internal tritium radiation doses in a single intake exceeded 2 mSv. The occupational population with the largest total internal tritium radiation doses consists of maintenance personnel, fuel operators, and radiation protection personnel, whose collective doses of internal exposure account for 75.51% of the total collective doses within the plant. Over 15 years of operation, the internal tritium radiation doses of workers in the Third Qinshan Nuclear Power Plant have been strictly controlled within the national regulatory limit and power plant management target, ensuring the health and safety of the workers.

Application of a generalized bottleneck routing problem to the task of adhering to acceptable doses of radiation during the dismantling of radiation hazardous objects

The paper considers the bottleneck routing problem, the prototype of which is the task of minimizing the radiation dose of workers during the performance of work related to disassembly of radiation-hazardous equipment. The authors proposed an optimal algorithm for solving the problem, which is based on the dynamic programming method. Its effectiveness is illustrated by example.

Issues of assessment of doses from natural sources in working conditions: implications for the unified state system of individual dose monitoring

The aims of the work are: 1) an analysis of information on radiation doses from natural sources of ionizing radiation of employees of enterprises in some industries of the Russian Federation and 2) an assessment of the state of registration of doses from natural sources in working conditions in the Unified System of Individual Dose Control. Materials and methods. The analysis was performed on the results of the operation of the Federal database of radiation doses of the population due to natural and artificial radiation background in 2013–2015 on the basis of the forms of the Federal statistical observation No. 4-DOZ in terms of collecting information on the radiation doses of workers in some non-nuclear industries due to natural sources of ionizing radiation. Results. Analysis of enterprises in 17 industries in 23 regions of Russia connected with the specificity of production processes showed cases of natural exposure of workers at the dose level exceeding 5 mSv/year. We have identified those branches of industry, for which the doses were close to 5 mSv/year.Examples of reducing the radiation doses by reducing the time spent by workers in workplaces with high levels of radiation are given. The problems of insufficient representativeness of the sample data are due to the lack of interaction of the management of industrial enterprises with the bodies of the Rospotrebnadzor. The obtained data allow speaking about the problem of assessing the quality of radiation control in the organizations where additional exposure of workers from natural radiation sources is expected. It is necessary to create a system of regulatory and procedural documents to solve the problem at the national level.

Description of the behavior of an aquifer by using continuous radon monitoring in a thermal spa

Radon (222Rn) levels in air and water have been analyzed continuously for almost a year in Las Caldas de Besaya thermal spa, north Spain. Radon is a naturally occurring noble gas from the decay of radium (226Ra) both constituents of radioactive uranium 238 series. It has been recognized as a lung carcinogen by the World Health Organization (WHO) and International Agency for Research on Cancer (IARC). Furthermore the Royal Decree R.D 1439/2010 of November, 2010 establishes the obligation to study occupational activities where workers and, where appropriate, members of the public are exposed to inhalation of radon in workplaces such as spas. Together with radon measures several physico-chemical parameters were obtained such as pH, redox potential, electrical conductivity and air and water temperature. The devices used for the study of the temporal evolution of radon concentration have been the RTM 2100, the Radon Scout and gamma spectrometry was complementarily used to determine the transfer factor of the silicone tubes in the experimental device. Radon concentrations obtained in water and air of the spa are high, with an average of 660Bq/l and 2900Bq/m3 respectively, where water is the main source of radon in the air. Radiation dose for workers and public was estimated from these levels of radon. The data showed that the thermal processes can control the behavior of radon which can be also influenced by various physical and chemical parameters such as pH and redox potential.

ADEPTTM: An innovative tool to reduce worker exposure using virtual job planning

Advanced Dose Exposure Planning Tool (ADEPT{sup TM}) is an innovative solution that assists nuclear station staff to effectively minimize the worker's radiation dose during the inspection and maintenance activities and to improve ALARA job planning. ADEPT{sup TM} provides 3D virtual reality job simulations for radioactive environments around the reactor components. ADEPT{sup TM} allows power plant workers to realistically guage the radiation dose without physically being exposed. (author)

Radiation shielding is not a solution – radiation protection of air crews

Abstract In most working environments it is fairly easy to minimize radiation doses of workers as postulated by radiation protection basics: Increasing the distance to the radiation source, reducing the exposure time, and the use of protective clothing or shielding. With air crews however, being the largest group of exposed persons and receiving the highest collective doses, classical protective measures are difficult or even impossible to enforce. Without neglecting the economical situation, effective measures could nevertheless be realized. Planning flights at slightly lower altitudes and further away from the geomagnetic poles can significantly reduce the radiation exposure for both crew and passengers. Furthermore, affordable high-quality dosimeters with the size of mobile phones have reached marketability. If installed on board, they could measure and display the actually received radiation during normal operation and additionally warn the flight crew in case of an abnormally high dose rate during solar particle events. Pilots could react to such warnings according to procedures that are yet to be installed.

Characterization of radiation fields and dose assessment from fuels manufacturing for advanced fuel cycles

The purpose of this study was to examine radiological hazards introduced to workers from the fabrication of fuels with minor actinides (MA) and reprocessed uranium (RepU) and determine the feasibility of using shielded gloveboxes instead of remotely controlled operations in hot cells. Of particular concern is the increase in photon source term from the daughter products in RepU and the mixed neutron and photon fields introduced by MA recycle. In the interest of keeping the glovebox worker's radiation dose as low as reasonable achievable (ALARA), dose rates were calculated for various typical and bounding fuel compositions for light water reactors (LWR) and fast reactor (FR) mixed oxide (MOX) fuels with and without MA. The impact of varying the separation efficiency of americium (Am) and curium (Cm) was examined because current separation processes in reprocessing and recycling do not allow for the complete separation of Am from Cm. The additional Cm will cause a significant increase in the neutron source term. The sensitivity of the fuels to aging time was also examined by decaying the recycled feedstocks from 6 months to 3 years to simulate the effect of delays in reuse of recycled materials. The highest photon and neutron sources were used to calculate the additional shielding requirements that would be needed for fuel fabrication. Through insight gained from this study, it can be concluded that a standard glovebox with one quarter inch stainless steel walls can be used to fabricate fuels with Am with little to no additional shielding. The introduction of small amounts of Cm in the fuels will require the fuel fabrication to be preformed remotely in hot cells. Thus, stressing the importance of developing methods to increase the separation efficiency of Am from Cm.

Measuring TL and OSL of beta radioisotopes inside a glove box at a radiopharmacy laboratory

Beta radiation emitters have been intensively used in therapeutic protocols, causing the increase of the radiation exposure of the workers. The thermoluminescent (TL) technique is largely utilized for the monitoring of beta radiation doses of workers. However, recently, the optical stimulated luminescence (OSL) technique has been shown useful for individual dosimetry and for beta radiation. In this study, the results obtained using Al2O3:C (OSL) and CaSO4:Dy (TL) detectors to measure beta absorbed doses inside a glove box at a radiopharmacy laboratory were compared.

Recent activities on tritium technologies of BA DEMO-R&D program in JAEA

The R&D for tritium technologies to a demonstration reactor (DEMO) are planned to be carried out in the Broader Approach (BA) program in Japan by JAEA with Japanese universities: (1) tritium analysis technology; (2) basic tritium safety research; and (3) tritium durability test. The EU joins the discussions and assessment of the R&D results. As the recent activities on the tritium technologies of the BA program, a multi-purpose RI facility, where the above R&D subjects will be carried out, has been designed in detail. A preliminary safety study has also been carried out for the amount of tritium released to the environment and for the radiation dose of workers. The facility is now under construction at Rokkasho in Aomori. The main subjects of the R&D of tritium analysis are the technologies for real-time analysis for hydrogen isotopes, gas, liquid and solid (such as microGC and calorimeter). The materials of interest include F82H, SiC, ZrCo, solid and liquid advanced breeder and multipliers. In the tritium durability tests, organic materials and metals planned to be used in a DEMO plant are studied for the radiation and the corrosion damage. A series of preliminary studies for the above subjects has been started.