• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2008.05a
• /
• pp.59-60
• /
• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2016.05a
• /
• pp.401-402
• /
• 2016

• Journal of the Korean Society of Radiology
• /
• v.6 no.4
• /
• pp.281-290
• /
• 2012

The difference of radiation dose of MDCT due to different protocols between hospitals was analyzed by CTDI, DLP, the number of Slice and the number of DLP/Slice in 30 cases of the head, the abdomen and the chest that have 10 cases each from MDCT examination of the department of diagnostic imaging of three general hospitals in Gyeongsangbuk-do. The difference of image quality, CTDI, DLP, radiation dose in the eye and radiation dose in thyroid was analyzed after both helical scan and normal scan for head CT were performed because a protocol of head CT is relatively simple and head CT is the most frequent case. Head CT was significantly higher in two-thirds of hospitals compared to A hospital that does not exceed a CTDI diagnostic reference level (IAEA 50mGy, Korea 60mGy) (p<0.001). DLP was higher in one-third of hospitals than a diagnostic reference level of IAEA 1,050mGy.cm and Korea 1,000mGy.cm and two-thirds exceeded the recommendation of Korea and those were significantly higher than A hospital that does not exceed a diagnostic reference level (p<0.001). Abdomen CT showed 119mGy that was higher than a diagnostic reference level of IAEA 25mGy and Korea 20mGy in one-third. DLP in all hospitals was higher that Korea recommendation of 700mGy.cm. Among target hospitals, C hospital showed high radiation dose in all tests because MPR and 3D were of great importance due to low pitch and high Tube Curren. To analyze the difference of radiation dose by scan methods, normal scan and helical scan for head CT of the same patient were performed. In the result, CTDI and DLP of helical CT were higher 63.4% and 93.7% than normal scan (p<0.05, p<0.01). However, normal scan of radiation dose in thyroid was higher 87.26% (p<0.01). Beam of helical CT looked like a bell in the deep part and the marginal part so thyroid was exposed with low radiation dose deviated from central beam. In addition, helical scan used Gantry angle perpendicularly and normal scan used it parallel to the orbitomeatal line. Therefore, radiation dose in thyroid decreased in helical scan. However, a protocol in this study showed higher radiation dose than diagnostic reference level of KFDA. To obey the recommendation of KFDA, low Tube Curren and high pitch were demanded. In this study, the difference of image quality between normal scan and helical scan was not significant. Therefore, a standardized protocol of normal scan was generally used and protective gear for thyroid was needed except a special case. We studied a part of CT cases in the local area. Therefore, the result could not represent the entire cases. However, we confirmed that patient's radiation dose in some cases exceeded the recommendation and the deviation between hospitals was observed. To improve this issue, doctors of diagnostic imaging or technologists of radiology should perform CT by the optimized protocol to decrease a level of CT radiation and also reveal radiation dose for the right to know of patients. However, they had little understanding of the situation. Therefore, the effort of relevant agencies with education program for CT radiation dose, release of radiation dose from CT examination and addition of radiation dose control and open CT contents into evaluation for hospital services and certification, and also the effort of health professionals with the best protocol to realize optimized CT examination.

• Journal of Digital Convergence
• /
• v.10 no.2
• /
• pp.249-254
• /
• 2012

Assessing the exposure dose and the obtained image during the abdominal radiography with 128-slice MDCT scanner and 4-slice MDCT scanner which are recently being used in clinics using the body tissue-equivalent phantom and the glass dosimeter, the results were as follows. During the CT test for the abdomen, the absorbed dose was $35.8{\pm}0.46mGy$ in 4-MDCT, and $19.03{\pm}0.25mGy$ in 128-MDCT, which indicated that the radiation dose necessary to obtain the image meaningful to diagnosis was required less by 128-MDCT(P<0.05). As a result of analyzing the image obtained from the abdominal test using MDCT with a 5-point Likert scale, 4-MDCT showed the result of 3.52 points, and 128-MDCT showed the result of 4.01 points, that is, the image quality of 128-MDCT was evaluated high, and there was a statistically significant difference. In the results above, it is considered that 128 slice MDCT scanner will be much used later as it can reduce the radiation exposure, and make us obtain the high quality of image.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.476-484
• /
• 2005

This paper is to evaluate rather correctly $C^{14}$ ingestion dose that inhabitants around PWR plants can receive, and draw how to apply TF(Transfer Factor) to evaluate dose by the ingestion of animal products. For this, in this paper, dose assessment and analysis about existing materials related to TF were carried out, and the methodology to present TF was based on dose assessment and analysis result. The ingestion dose calculated using TFs presented by CSA and KEPRI was high or equal compared with SAM(Specific Activity Model) which is the most conservative, on the other hand, TFs given by NEC did not consider the effect according to volume change of animal at all, Therefore, it is judged that models used in the existing codes to asses the $C^{14}$ concentration into animal products must be improved to apply fundamentally hybrid model using transfer factors, that transfer factor on each animal products have to be developed through experiment for applying to our county.

• Journal of Radiation Protection and Research
• /
• v.37 no.4
• /
• pp.226-230
• /
• 2012

The gross alpha analysis of nasal smear samples for the radiation emergency and the additional follow-up steps were established. Cotton swab sticks using in local hospitals for nasal smear in Korea were used for the verification. The measurement results of standard samples spiked with certified reference source were well agreed within ${\pm}20%$ compared with reference values. The clearance ratio of smear samples conducted with wet smear condition showed higher value. To eliminate the quenching effect of liquid scintillation samples, dry of smear samples should be followed up before counting samples. Based on the measurement results, medical decision levels and internal dose assessment were established for the victims in the beginning of radiation emergency.

• Journal of the Korean Society of Radiology
• /
• v.16 no.3
• /
• pp.273-279
• /
• 2022

In order to reduce the absorbed dose given to the patient during dental radiography, a sensor that inserts a shield into the intraoralsensor was designed. Using the designed sensor, the change in absorbed dose depending on whether or not a shield was used was evaluated. The system used to evaluate the absorbed dose is VEX-S300C from Vatech, and the energy spectrum of X-rays was obtained through SPEKTR simulation based on the irradiation conditions of 65 kV, 3 mA, and 0.15 sec, and the number of photons for each energy was derived. After designing the system through Genat4 Application for Tomographic Emission(GATE) simulation, the energy spectrum obtained was used as a radiation source to calculate the absorbed dose. Lead was used for the shield, and simulations were performed at 0.1 mm thickness intervals from 0.1 mm to 0.5 mm was evaluated. In the case of using an X-ray field with a diameter of 60 mm, the decrease in absorbed dose according to the presence or absence of a shield decreased exponentially as the thickness of the shield increased. In addition, when a 20 mm × 30 mm field was used, the absorbed dose was significantly reduced even when no shield was used, and it was confirmed that the absorbed dose was further reduced when a shield was used.

• Journal of Radiation Protection and Research
• /
• v.39 no.4
• /
• pp.213-217
• /
• 2014

Medical operations and diagnosis using interventional radiology techniques have been increased. The management and monitoring of occupational radiation exposure to the staff of interventional radiology become important, specially because they stand in close proximity to the patient. The operational radiation protection quantity, Hp(10) which can be obtained from personal dosimeter do not always represent the effective dose to the staff. So, in this study, to estimate the critical organ doses to the staff of interventional radiology, Monte Carlo calculations with mathematical human phantom and dose measurements with personal dosimeters were carried out for the major interventional radiology procedures using C-arm. Results showed that the values of Hp(10) measured by personal dosimeters were higher than critical organ doses which were calculated. And the calculated dose to thyroids was much higher than those of other critical organ doses. For the proper radiation protection of the medical staff of interventional radiology, additional radiation protection for thyroids as well as for whole body shielding like wearing a lead apron should be considered.

• Journal of the Korea Academia-Industrial cooperation Society
• /
• v.10 no.7
• /
• pp.1760-1765
• /
• 2009

After administration of a radiopharmaceutical, the patient remains radioactive for hours or even days, representing a source of potential radiation exposure. Thus, including the personnel who are occupationally exposed to ionizing radiation, radiation exposure must be managed for members of the public, in particular for people accompanying patients. In this study we investigated radiation exposure dose management in the nuclear medicine departments at seven general hospitals. Two of them had no radiation safety considerations for patient transporters, sanitation workers and the like. And they all were careless of radioprotection for people accompanying patients. The average dose rate to people accompanying patients from radioactive patients just before a bone scan was 25.60 ${\mu}$Sv h-1. This is higher than 20 ${\mu}$Sv $h^{-1}$which is the annual public dose limit for temporary use. Therefore radiation dose measurement and risk assessment of patient transporters, sanitation workers and the like should be performed. And the nuclear medicine technologist should provide advices on the radiation safety to patient transporters, sanitation workers, people accompanying patients and so on. To ensure the radiation safety for people accompanying patients, it is required to restrict the patient's access to his relatives, friends and other patients or isolate patients.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.52-57
• /
• 2004

In order to analyze key parameters of important radionuclides in dose evaluation model of decommissioning site, a sensitivity analysis was performed. This analysis assumed a resident farmer for an exposure scenario and 0.037Bq/g for the concentration of radionuclides. As a result of sensitivity analysis, the key parameters of radionuclides considered were the area of contaminated zone, external gamma shielding factor and indoor time fraction for Cs-137 and Co-60. The key parameters for C-14 were the environmental parameters and hydrological parameters of unsaturated zone. Also, the key parameter for Sr-90 was the density of contaminated zone.