Total Collective Dose Research Articles

THE INFLUENCE OF THE QUALITY OF X-RAY IMAGES FROM TELEMEDICINE ON THE COLLECTIVE EFFECTIVE DOSE OF PATIENTS

Ensuring a quality of diagnostic radiology along with increasing efficiency is a key task for healthcare system for both municipal medical facilities and private medicine. When a defective X-ray image is obtained, there is a need to re-conduct a examination, which in turn entails reputational, temporary and economic losses for a medical facility. Repeated examination makes an additional contribution to the patient’s radiation exposure also. The paper shows that for facilities providing telemedicine services, implementation of a clinical audit for diagnostic examinations using information technology is efficient. In 2022 2059 error x-ray images were identified applying a similar system, which is 0.084% of the total number of telemedicine radiology examinations. A collective effective dose due to defective examinations was 3,613 man-Sv, which is less than 0.11% of the total collective dose.

Assessment of Occupational Radiation Exposures at Ghana Research Reactor-1 Facility.

The annual occupational doses for workers at the Ghana Research Reactor-1 facility were assessed for the period 2018-2021. The dose records of monitored staff were retrieved and analysis done for dose distribution and collective effective doses. Thermoluminiscent dosimeters were used to monitor the occupational exposures. The dosimeters were evaluated for the cumulative radiation dose levels using the Harshaw 6600 TLD reader system. Annual dose of 1.52 mSv/year was the maximum acquired by an individual. An annual average effective dose range of 0.20-1.36 mSv was determined for all workers. The annual total collective effective dose was established to be in the range of 0.40-10.08 man-Sv. The 20 mSv annual limit for occupational exposure was not exceeded for monitored workers. The assessment shows that the GHARR-1 facility, in terms of radiation health effects, is a favorable environment for workers since exposures are mostly below occupational exposure limit.

Feasibility study for the evaluation of doses received by organs during medical exposure for pediatric patient undergoing CT scan and estimation of the potential risk of radiation-induced cancers

Computed Tomography (CT) continues to contribute a significant portion of the total collective dose delivered to the public from medical procedures involving ionizing radiation. Children are considered to be at higher risk of developing radiation induced cancer due to the young age of exposure and increased tissue radio sensitivity. Organ dose estimation is essential for pediatric patient cancer risk assessment. The aim of this study was to evaluate the excess risk of radiation induced cancer following exposure to low-dose ionizing radiation from pediatric CT scans.We collected information from Radiation Dose Structured Report (RDSR) in 2 radiology department for 3 protocols and three (3) different age group in pediatric CT scan.We estimated the excess of cancer risk by using the Radiation Risk Assessment Tool RadRAT). For that, we calculate first the organ doses with National Cancer Institute for CT (NCICT). Effective dose and Size Specific Dose Estimate were also estimated, CTDI and DLP recorded from the RDSR were compared by the ones given by the software. The doses received by 30 organs including both inside and outside the scanning range were calculated and compared for the different age groups and protocols.The excess risk observed here range between 0.6 and 10.1‰ for respectively the thorax and Abdomen protocol in boy's cohort. This can be due to the significant dose variability observed among radiological protocols defined for the same CT scan and patient of the same age. For a head examination, a ratio of 2–4, depending on the age of the child, is estimated between the maximum and minimum doses delivered to the brain. For the other types of examination, this ratio is even greater: around 9 for chest examinations, 16 for abdominopelvic explorations.Careful justification of pediatric CT scans and dose optimization should be available in hospitals to minimize risks.

The Use of Genotoxicity Endpoints as Biomarkers of Low Dose Radiation Exposure in Interventional Cardiology.

The effect of the reportedly low ionizing radiation doses, such as those very often delivered to patients in interventional cardiology, remains ambiguous. As interventional cardiac procedures may have a significant impact on total collective effective dose, there are radiation protection concerns for patients and physicians regarding potential late health effects. Given that very low doses (<100 mSv) are expected to be delivered during these procedures, the purpose of this study was to assess the potency and suitability of current genotoxicity biomarkers to detect and quantitate biological effects essential for risk estimation in interventional cardiology. Specifically, the biomarkers γ-H2AX foci, dicentric chromosomes, and micronuclei, which underpin radiation-induced DNA damage, were studied in blood lymphocytes of 25 adult patients before and after interventional cardiac procedures. Even though the mean values of all patients as a group for all three endpoints tested show increased yields relative to baseline following medical exposure, our results demonstrate that only the γ-H2AX biomarker enables detection of statistically significant differences at the individual level (p < 0.001) for almost all patients (91%). Furthermore, 24 h after exposure, residual γ-H2AX foci were still detectable in irradiated lymphocytes. Their decline was found to vary significantly among the individuals and the repair kinetics of γ-H2AX foci was found to range from 25 to 95.6% of their maximum values obtained.

Analysis on monitoring results of individual dose of occupational external radiation among radiation workers in Lanzhou in 2019

Objective: To analyze the individual dose level of occupational external radiation of radiation workers in Lanzhou in 2019, so as to provide reference for radiation protection and occupational health management. Methods: In April 2020, a total of 1460 radiation workers in Gansu Provincial Center for Disease Control and Prevention in 2019 were selected as the research objects. The unit nature, hospital level and occupational category of the monitored workers were collected, and the monitoring results of external radiation personal dose in 2019 were analyzed and compared. Results: In the occupational external radiation monitoring of radiation workers in Lanzhou in 2019, the effective dose of 48 persons was 1.0~<5.0 mSv, the effective dose of 2 persons was 5.0~<10.0 mSv, the annual collective effective dose was 308.21 people·mSv, and the average annual effective dose of monitored persons was 0.21 mSv/a. There was significant difference in the distribution of annual effective dose per capita among different occupational groups (H=34.43, P<0.05) . The annual effective dose per capita of nuclear medicine personnel was higher (0.56 mSv/a) , followed by interventional radiology (0.33 mSv/a) . The ratio of annual collective dose to total annual collective dose with annual individual dose more than 5 mSv (SR(5)) and the ratio of the number of staff with annual individual dose more than 1mSv to the total number of monitored personnel (NR(1)) were higher in nuclear medicine and interventional radiology personnel. The average annual effective dose distribution of diagnostic radiologists in different level hospitals was statistically significant (H=16.46, P<0.05) . The average annual effective dose in private hospitals, community hospitals and health centers was higher (0.32 mSv) , followed by county hospitals (0.23 mSv) . Conclusion: The individual dose of occupational external radiation of radiation workers in Lanzhou is generally low, and the annual effective dose of nuclear medicine and interventional radiology workers is high. The management of radiation protection should be emphasis on this people. And it is suggested to strengthen the supervision of private hospitals and update and maintain the equipment of community health centers.

Radiological aspects during cutting and removal of L-08 coolant channel from the core of 540 MWe TAPS-4 nuclear reactor

The pressurized heavy-water reactors (PHWR) consist of a low-pressure horizontal reactor vessel, calandria, containing heavy water as moderator. The calandria is pierced by a large number of coolant tubes (also called pressure tubes [PTs], 392 in 540 MWe PHWR), which contains fuel bundles, and through which pressurized heavy-water coolant circulates. During biennial shut down in 2017, in-service inspection of coolant channels in Tarapur atomic power station-4 (TAPS-4) had been carried out and after the review of results of inspection, it was recommended by various groups of experts that channel L-08 should be removed for postirradiation examination at Bhabha Atomic Research Center (BARC). Before the channel removal job, one special shielding flask was designed to shift the removed channel to BARC. The integrity test of special shielding flask was carried out by safely placing cobalt-60 (source strength 851000 MBq) capsule source inside the shielding flask with the help of cranking unit mechanism followed by dose rate mapping on the outer surface of the flask. To establish the hydrogen pickup rates in L-08 PT, sliver samples were collected and separately sent to BARC. Four metallic sliver samples were obtained at four different distances from north E-face. The activity content present in each sliver sample was also estimated. The maximum activity estimated was 2313.24 MBq. Subsequently, L-08 coolant channel was cut from both sides using a chipless tool. Jobs involving heavy water (D2O) collection work were carried out with a ventilated plastic suit. Derived air concentration (DAC) of tritium at the work location was maintained below 1DAC during the entire activity. Particulate DAC was found below the detectable limit. Floor contamination checks and floor decontamination were conducted at regular intervals to avoid buildup of contamination. As a result of such high-quality radiological safety measures, only 25 workers, out of 270 radiation workers, have received a cumulative dose of more than 3 mSv in direct reading dosimeter with a maximum individual dose of 8.45 mSv and maximum individual uptake of 0.39 GBq/m3. Job was completed with a total collective dose of 324.35P-mSv which is 14.5% lower than estimated. This article highlights some of the critical tasks involved in the cutting and the removal of irradiated coolant channel from the core of 540 Mwe TAPS-4 reactor which is a first of kind activity in nature.

MRI Screening of Lungs in the COVID-19 Pandemic at the Stages of Medical Care as a Tool to Reduce the Total Collective Dose of Radiation to the Population

Objective: to evaluate the role and place of MRI lung screening in the detection of pneumonia and patient routing.Material and methods. 500 MRI tests were performed in the period from November 1, 2020 to December 15, 2020 on the basis of more than 20 diagnostic centers of the federal MRI-Expert network. Two groups were identified. In Group 1 (control, n = 50) MRI studies were compared with CT studies in a single time interval of 0–2 days; 25 patients had a positive PCR test for SARS-CoV-2 and 25 patients were conditionally healthy. In Group 2 (effective, n = 450) mediastinal MRI was performed with lung screening on Philips 1.5 T and Siemens 1.5 T devices. The statistical analysis of the medical data base was performed.Results. During the study, mandatory and additional MRI scanning programs were identified: for Philips 1.5 T tomograph, the mandatory programs are sSSh_fb: tra and cor; THRIVE: tra (inhale/exhale); for Siemens 1.5 T – T2_BLADE: cor, tra, sag. When comparing the visual data of the control group (n = 25) with a positive PCR test in a single time interval of 0–2 days, the fact of detecting MR changes coincided with CT changes in 76% of cases (n = 19). The group of patients were examined by only one method – MRI-screening of the lungs (n = 475), pathological changes in the lungs were detected in 44% (n = 209). Localizations of the pathological changes were as follows: bilateral changes – 70.3% (n = 147), right-side changes – 19.6% (n = 41), left-side changes – 10% (n = 21); lower parts 26.8% (n = 26), average departments – 10% (n = 21), the upper divisions – 14.8% (n = 31), mid-lower 29.6% (n = 62), total – 18.6% (n = 39). The ranges of the area of lesion of the pulmonary parenchyma on MRI were graded according to MRI criteria into 4 groups (&lt; 25%, 25 – 50%, 50 – 75%, &gt; 75%). The collective radiation dose decrease was calculated for a group of patients (n = 450), which averaged 2.025 man-Sv for 1.5 months, of which 0.077 man-Sv were control studies.Conclusion. Based on the results obtained, the analyses of the possibilities of the MRI method in displaying pulmonary changes was performed. The method of MRI screening of the lungs is recognized as a possible alternative to computed tomography for dynamic monitoring in conditions of a shortage of CT records or the inability to perform it, and as a tool to reduce the collective effective dose of radiation to the population.

Status and Trend of Occupational Radiation Exposure in Radiotherapy and Diagnostic X-ray Practices in Bangladesh

Introduction: The evaluation of occupational exposure and related trends due to external ionizing radiation in diagnostic and therapeutic purposes has become crucial to understand the implementation of regulatory acts and technological advancement. This study describes the status of occupational radiation exposure in radiotherapy (RADT) and diagnostic X-ray (DRA) sector and the comparison with related research.Materials and Methods: Overall, 12141 number of radiation workers were monitored using thermoluminescent dosimeters (TLDs) which read-out by Harshaw TLD Reader (Model 4500) on a quarterly basis. Several parameters such as annual collective effective dose, average annual effective dose, collective and individual dose distribution, and the probability of cancer risk were analyzed.Results: The number of monitored workers increased by around 35%, whereas the number of radiation workers received a measurable amount of doses decreased by around 37% during 2014-2018. The annual average effective doses in RADT and DRA were in the range of 0.017-0.1112 and 0.076-0.1702 mSv, respectively. The results indicate that more than 94% of the total collective dose was for the non-physician group. Among exposed radiation workers, almost 78% received doses below 1mSv and

CONTEMPORARY COLLECTIVE EFFECTIVE DOSE TO THE POPULATION FROM X-RAY AND NUCLEAR MEDICINE EXAMINATIONS-CHANGES OVER LAST 10 YEARS IN FINLAND.

Contemporary collective effective doses to the population from x-ray and nuclear medicine examinations in Finland in 2018 was estimated. The estimated effective dose per caput from x-ray examinations increased from year 2008 to 2018 respectively from 0.45 mSv to 0.72 mSv and from nuclear medicine examinations from 0.03 mSv to 0.04 mSv. The proportional dose due to CT examinations of the total collective effective dose from all x-ray examinations increased from 58% in 2008 to 70% in 2018 and the dose did not change substantially in total when new conversion factors were applied. The collective effective dose from conventional plain radiography did not change substantially during the last ten years while the new (ICRP 103) tissue weighting factors were taken into use in 2018, however frequencies of examinations in total decreased. The collective effective dose from CT in nuclear medicine tripled between 2009 and 2018.

Patient Exposure from Radiologic and Nuclear Medicine Procedures in the United States: Procedure Volume and Effective Dose for the Period 2006-2016.

Background Comprehensive assessments of the frequency and associated doses from radiologic and nuclear medicine procedures are rarely conducted. The use of these procedures and the population-based radiation dose increased remarkably from 1980 to 2006. Purpose To determine the change in per capita radiation exposure in the United States from 2006 to 2016. Materials and Methods The U.S. National Council on Radiation Protection and Measurements conducted a retrospective assessment for 2016 and compared the results to previously published data for the year 2006. Effective dose values for procedures were obtained from the literature, and frequency data were obtained from commercial, governmental, and professional society data. Results In the United States in 2006, an estimated 377 million diagnostic and interventional radiologic examinations were performed. This value remained essentially the same for 2016 even though the U.S. population had increased by about 24 million people. The number of CT scans performed increased from 67 million to 84 million, but the number of other procedures (eg, diagnostic fluoroscopy) and nuclear medicine procedures decreased from 17 million to 13.5 million. The number of dental radiographic and dental CT examinations performed was estimated to be about 320 million in 2016. Using the tissue-weighting factors from Publication 60 of the International Commission on Radiological Protection, the U.S. annual individual (per capita) effective dose from diagnostic and interventional medical procedures was estimated to have been 2.9 mSv in 2006 and 2.3 mSv in 2016, with the collective doses being 885 000 and 755 000 person-sievert, respectively. Conclusion The trend from 1980 to 2006 of increasing dose from medical radiation has reversed. Estimated 2016 total collective effective dose and radiation dose per capita dose are lower than in 2006. © RSNA, 2020 See also the editorial by Einstein in this issue.

RESULTS OF CZECH NATIONAL STUDY OF RADIATION EXPOSURE FROM RADIOTHERAPY OF NON-MALIGNANT DISEASES, IN PARTICULAR OF HEEL SPURS.

About 26000 patients are treated per year with radiotherapy for non-malignant diseases in the Czech Republic. Approximately 75% of them are treated on X-ray therapy units and most of these patients undergo radiotherapy of heel spurs. The evaluation of radiation exposure of these patients was based on measured organ doses and on data from clinical practice. Collective effective doses for particular diagnoses were calculated in order to compare doses resulting from different diagnoses treated on X-ray therapy units. The collective effective dose from radiotherapy of heel spurs in the Czech Republic in 2013 was evaluated to 77 manSv. It represents 25.6% of the total collective effective dose for all diagnoses of radiotherapy for non-malignant diseases treated on X-ray therapy units.

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.

Assessment of the health damage costs of radionuclides releases from Muğla provinces lignite-fired power plants

Abstract The health impacts and corresponding damage costs of radioactive emission of Muğla province lignite-fired power plants have been assessed by using the simplified impact pathway approach. Radiation dose and risk calculations have been carried out by the code CAP88-PC around the power plants. Specific isotopes, 238U, 232Th, 226Ra and 40K in the flying ash samples are considered as radioactive sources. Power plants intersecting regions are also considered in the collective dose calculation. The estimated total collective dose around Muğla province due to Yatağan, Yeniköy and Kemerköy power plants is 5.25 × 10−2 man.Sv/year. The total health effects damage cost around the Muğla province due to the radioactive emissions from the power plants is 2504.3 US $ 2000/year. The results obtained from the calculations are under the dose limits of International Commission of Radiation Protection and it does not any risk for public health around the plant environment.

Level of Practical Skills in Personnel Dosimetry Monitoring and the Laboratory Experience with Different Types of TLD Readers

This study was carried out to analyze individual annual dose records of diagnostic radiology staff at forty-eight (48) different medical facilities in urban and rural Region of Ghana for the period of 2011-2015. The monitored dose data were extracted from the Radiation Protection Institute of the Ghana Atomic Energy Commission’s database called the Dose Management System (DMS). The doses of these OEWs analyzed, are divided into four subgroups namely; general radiographers, radiologists, computed tomography (CT) technologists, fluoroscopy technologists. The dose distribution, collective dose and mean annual dose were determined. A total of 1574 OEWs were monitored comprising of 56% radiographers, 15% radiologist, 21% computed tomography (CT) technologists and 8% fluoroscopy technologists. The average annual effective dose ranged from 0.36 to 1.70 mSv with radiographers receiving the largest. Fluoroscopy technologist recorded the least annual total collective effective dose value of 0.1 person-Sv. The study contributes to the existing works to promote a more comprehensive personal monitoring service for OEWs. Continued analysis of occupational doses should be an integral component of institutional radiation safety programs in Ghana.

Exposure of the Population of Ngaoundere-Cameroon to Ionizing Radiation Related to Medical Diagnosis in 2018

Background: Medical applications are the main source of exposure to ionizing radiation of human origin. Our objective was to determine the data on exposure to ionizing radiation of medical origin of the population of Ngaoundere in 2018. Methodology: It was a cross-sectional descriptive study conducted within a period of one year, in the different hospitals of Ngaoundere, with a functional medical imaging service. The variables studied were age, sex, type of examination, anatomical region and effective dose. The statistical analysis was performed using the Microsoft Office 2016 software, Sphinx V5; the effective dosage was calculated using the Internet Dose calculation Module. Results: In 2018, 4136 diagnostic acts using ionizing radiation were carried out; it concerned only conventional radiology with an average of 0.02 per capita. The total collective dose received by the population was 8300 mSv, and an average dose of 0.040 mSv per inhabitant. The proportion of the population that has actually benefited from a conventional radiology examination is 2.07%, an individual effective average dose of 2 mSv. The most frequent acts involved the thorax, limbs, spine and pelvis with respectively 53.9%; 19.6%; 14.3% and 6.7%. Acts involving the spine, pelvis and hip, skull and abdomen contributed to the majority of the collective effective dose respectively with 45.75%, 25.96%, 10.53% and 8.84%. The age group performing most exams in men is 25 to 49 and 25 to 54 in women; the number of acts is higher among men 2457 (59.4%) acts compared to women 1679 (40.6%) acts. The collective dose per sex is higher among women with 4487.22 mSv (54.06%) compared to men with 3812.98 mSv (45.94%). Conclusion: Only 2.07% of population of Ngaoundere benefited from a conventional radiology examination in 2018 with an individual effective average dose of 2 mSv. The annual per capita number of acts is 0.02 and annual per capita effective dose is 0.040 mSv in Ngaoundere in 2018.

Patient effective doses and radiation risks in cardiac catheterization procedures

Cardiac catheterizations (CC) represent a set of interventional procedure used in the diagnosis and treatment of coronary arteries diseases. Whereas interventional procedures perhaps represent only some 12% of all radiological procedures they nevertheless contribute about 48% of the total collective dose worldwide. In a Sudanese based study, the objectives of present work have been to evaluate patient radiation dose and to estimate effective doses and cancer risks for three types of cardiac catheterization procedure. Radiation doses and the associated radiation risks have been evaluated for a total of 346 patients undergoing treatments for a range of clinical indications, including 187 Diagnostic Coronary Angiographic (DCA) procedures (54%), 118 Percutaneous Coronary Interventions (PCI) (34.1%) and 41 Pacemaker (PM) procedures (11.9%)). The respective effective dose ranges were 4.0- to 59.3 mSv, 11.4- to 175 mSv and 7.2- to 51.5 mSv. None of the present patient cohort developed tissue reactions, deterministic effects clearly being anathema in diagnostic radiological practice. With optimization of patient doses being fundamental to best practice, and with it an associated mitigation of stochastic risk, not least in regard to patients of younger age facing the greatest risk, there is particular concern regarding training and experience of radiographic staff, as results show.

Analysis of individual dose monitoring results among radiation workers in a first-class hospital at Grade 3 from 2010 to 2017

Objective: To understand the occupational external exposure dose among radiation workers in a first-class hospital at Grade 3 of Suzhou, and to provide reference for radiological protection. Methods: The individual dose of 1156 radiation workers in the hospital from 2010 to 2017 were detected, the annual collective effective dose and per capita annual effective dose were analyzed for different years, different occupations (diagnostic radiology, radiotherapy, nuclear medicine, interventional radiology) , gender, and age. Results: From 2010 to 2017, the total annual collective effective dose was 351.40 person·mSv, the per capita annual dose was 0.30 mSv/a, and radiation workers whose annual effective dose was less than 1 mSv accounted for 94.98%. There were 5 interventional radiology workers and 1 nuclear medicine worker with annual effective dose between 2 and 4 mSv. There was no worker with annual effective dose over 4 mSv. The per capita annual effective dose of nuclear medicine workers was the highest (0.40 mSv/a) . The per capita annual effective dose was not significantly different between radiation workers with different genders and ages (P>0.05) . Conclusion: Most of radiation workers have low individual dose level in the hospital. It is important to focus on nuclear medicine workers and interventional radiology workers.

OA202] Recent update of typical effective doses received by patients at diagnostic and interventional radiology procedures and its impact on assessment of collective effective dose to population in bulgaria

Purpose Performance of regular national patient dose surveys is required by European and International Basic Safety Standards and by National law. Third national patient dose survey (TNS) was conducted in 2016–2017 with aim of updating information on radiation exposure to patients at different diagnostic and interventional radiology (DIR) procedures. The purpose of this work is to assess and update typical effective doses received by patients at various diagnostic and interventional radiology procedures (DIR) and to find its impact on assessment of collective effective dose to population. Methods Values of typical patient doses (TPD) are based on data obtained during TNS. Typical effective dose (TED) for each procedure was calculated using conversion coefficients (CC) from TPD to effective dose (E) with dimensions: (mSv. Gy - 1 . cm - 2 ) for radiography, fluoroscopy and interventional procedures; and (mSv. mGy - 1 . cm - 1 ) for Computed tomography procedures respectively. Values of CCs are based on UNSCEAR recommendations, as for Chest radiography an own CC assessment is made based on kerma area product values and respective E values calculated using PCXMC software. Total collective effective dose to Bulgarian population ( S E ) and the effective dose per capita were calculated based on the number of the most frequent DIR procedures and the TED per procedure. Results TED are updated for 16 of most common DIR procedures of which: 5 are radiography; 4 – fluoroscopy; 4 – computed tomography; 2 – interventional cardiology and one is for mammography respectively. For year 2016 SE is assessed to 5868 man.Sv which relates to mean effective dose of 0.82 mSv per capita. It is 16.8% higher than its relevant assessment based on older information for not updated typical patient doses obtained during previous national survey performed in 2007. An increase of 84% in S E is observed for the period of 2007 to 2016 year, as dynamics of collective effective doses is analysed and discussed. Conclusions Updated assessments of TEDs and SE due to DIR procedures are elaborated. Regular patient dose surveys are important for update of National Diagnostic Reference Levels (NDRLs) as well as for obtaining more realistic and precise assessment of collective effective dose to population due to diagnostic radiology procedures.

Analysis of radiation safety for Small Modular Reactor (SMR) on PWR-100 MWe type

Indonesia as an archipelago country, including big, medium and small islands is suitable to construction of Small Medium/Modular reactors. Preliminary technology assessment on various SMR has been started, indeed the SMR is grouped into Light Water Reactor, Gas Cooled Reactor, and Solid Cooled Reactor and from its site it is group into Land Based reactor and Water Based Reactor. Fukushima accident made people doubt about the safety of Nuclear Power Plant (NPP), which impact on the public perception of the safety of nuclear power plants. The paper will describe the assessment of safety and radiation consequences on site for normal operation and Design Basis Accident postulation of SMR based on PWR-100 MWe in Bangka Island. Consequences of radiation for normal operation simulated for 3 units SMR. The source term was generated from an inventory by using ORIGEN-2 software and the consequence of routine calculated by PC-Cream and accident by PC Cosyma. The adopted methodology used was based on site-specific meteorological and spatial data. According to calculation by PC-CREAM 08 computer code, the highest individual dose in site area for adults is 5.34E-02 mSv/y in ESE direction within 1 km distance from stack. The result of calculation is that doses on public for normal operation below 1mSv/y. The calculation result from PC Cosyma, the highest individual dose is 1.92.E+00 mSv in ESE direction within 1km distance from stack. The total collective dose (all pathway) is 3.39E-01 manSv, with dominant supporting from cloud pathway. Results show that there are no evacuation countermeasure will be taken based on the regulation of emergency.

Diagnostic nuclear medicine procedures in Germany between 1996 and 2002: application frequencies and collective effective doses.

Man-made radiation exposure to the German population predominantly results from the medical use of ionizing radiation. It was therefore the aim of the present study, to provide public health information concerning diagnostic nuclear medicine procedures carried out in Germany between 1996 and 2002. Application frequencies for 10 groups of procedures were estimated from official reimbursement data provided by the German health insurance companies. Mean effective doses for these examinations were estimated from data provided by 14 clinics and 10 practices concerning the radiopharmaceuticals in use and the activities administered. During the period 1996-2002, a total of (3.83 +/- 0.31) million nuclear medicine procedures were performed in average per year, which corresponds to a mean annual application frequency of approximately 47 examinations per 1 000 inhabitants. More than 90% of the examinations were scintigraphies of the thyroid (37%), skeleton (25%), myocardium (13%), lungs (8%) and kidneys (8%). The averaged collective effective dose was (10.2 +/- 1.4) . 10(3) mSv per year, which corresponds to a mean annual per caput effective dose of about (0.12 +/- 0.02) mSv. Three types of procedures were responsible for about 80% of the total collective effective dose: scintigraphies of the myocardium (36%), skeleton (33%) and thyroid (10%). Averaged over all procedures carried-out, the mean effective dose per examination was (2.7 +/- 0.8) mSv. The average effective dose per inhabitant and year caused by nuclear medicine examinations is markedly lower than that resulting from medical X-ray procedures (0.12 vs. 1.8 mSv). Reduction of patient exposure may be achieved, for example, by replacing (201)Tl-labeled radiopharmaceuticals by (99m)Tc-labeled compounds.