• 대한방사선기술학회지:방사선기술과학
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• 제44권5호
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• pp.495-502
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• 2021

This study aims to provide basic data for elderly health insurance policy and medical radiation safety management by analyzing the general radiography usage and exposure dose of the elderly in Korea. The effective dose for each general radiography was calculated using the ALARA-GR program for 260 general radiography codes selected from 'National Health Insurance Care Benefit Cost'. The usage of general radiography was analyzed in the 2016 elderly patient data of the Health Insurance Review and Assessment Service, and the effective dose for each general radiography was applied. The general radiography usage and exposure dose per person aged 65 years and over was 6.47 cases and 0.56 mSv. Females showed higher value than males as 7.15 cases and 0.66 mSv(p<.001). By age, those between 75 and 79 showed the highest number as 6.97 cases and 0.62 mSv(p<.001). Those who were supported by Medical Aid showed higher value than those who were insured by National Health Insurance as 8.82 cases and 0.76 mSv(p<.001). In addition, the ratio by radiography was in the order of Chest 20.85%, Knee Joint 15.58%, and L-spine 14.67%, and the exposure dose was L-spine 29.40%, Chest 15.82%, Abdomen 7.97%, and Entire Spine 7.20%. General radiography, which is widely used due to the high frequency of diseases in the elderly population should be taken into consideration when establishing health insurance policies. In addition, it is necessary to check whether the general radiography with high exposure dose is performed as a routine examination without considering medical necessity.

• Journal of Radiation Protection and Research
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• 제46권3호
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• pp.106-111
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• 2021

Background: Crookes tube is utilized in junior high and high schools in Japan to study the character of electrons and current, and not for radiological education. There is no official guideline or regulation for these radiation source to the public. Therefore, most teachers have no information about the leakage of X-rays from Crookes tube. The peak energy of X-rays is approximately 20 keV, and it is impossible to measure using conventional survey meters. Materials and Methods: Each leakage dose of low energy X-rays from 38 Crookes tube in the education field, such as junior and senior high schools in Japan, was explored by the teachers in the school using radio-photoluminescence (RPL) dosimeters. Before and after the measurements, the dosimeters were sent by postal mails. Results and Discussion: At the exploration in this study, it was estimated that the 70 ㎛ dose equivalent, H_p(0.07) of X-rays from 31 Crookes tubes were smaller than 100 µSv in 10 minutes, at the distance of 1 m, where the Crookes tube was usually observed. However, the highest dose was estimated as 0.69 mSv by an equipment with the full power. Furthermore, one Crookes tube exhibited 0.62 mSv with minimum output power of the induction coil. This relatively large dose was reduced by the shorter distance of discharge electrodes of the induction coil. Conclusion: The leakage dose of low energy X-rays from 38 Crookes tube was explored using RPL dosimeters. It was estimated that the H_p(0.07) of X-rays from 31 Crookes tubes were smaller than 100 µSv in 10 minutes at the distance of 1 m, while some equipment radiated a higher dose. With this study, the provisional guideline for the safety operation of Crookes tube is established.

• 대한방사선기술학회지:방사선기술과학
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• 제42권2호
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• pp.105-111
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• 2019

A medical personnel could be placed beside a patient together in CT room to do Ambu-bag for a seriously ill patients or emergency patient. At this time, the medical personnel can be exposed indirect radiation unnecessarily. In this case, it is necessary to recognize indirect radiation dose levels and methods to reduce them using actual clinical CT protocols such as Chest, Abdomen, and Brain CT. We researched surface radiation dose with or without radiation protectors such as apron and goggles according to different distances far from gantry using two different CT scanners (Fixed MDCT and mobile CT). As a result, for Chest, Abdomen, and Brain CT with Fixed MDCT, indirect radiation dose on thorax portion were 0.047, 0.089, 0.034 mSv without apron. Also, those with apron were 0.007, 0.012, 0.006 mSv. In case of mobile CT, it was 0.014 mSv without apron and 0.005 mSv with apron. By using protectors and increasing the distance, we could reduce it to 97%. Systematic management is necessary based on the measured data in order to minimize radiation damage due to indirect exposure dose.

• 디지털콘텐츠학회 논문지
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• 제13권2호
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• pp.151-157
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• 2012

방사선 구역 내부의 공간선량은 의학의 발전과 더불어 방호시설이 잘 되어 있어도 작업종사자의 피폭을 증가시킬 우려가 있다. 핵의학과 내의 분배실은 항상 공간선량이 존재하므로 작업종사자의 피폭선량을 예측하기 위하여 분배실 내부의 공간선량을 측정, 분석 하였다. 핵의학과 $^{18}F$ 분배실의 공간선량률 측정결과 최대 $6.78{\pm}0.083{\mu}Sv/h$, $^{99m}Tc$, $^{131}I$ 분배실의 공간선량률이 최대 $9.248{\pm}0.013{\mu}Sv/h$로 나타났다. 또한, $^{18}F$ 분배실의 경우 1m 거리에서 간호사가 IV시 연간 외부피폭선량은 $42.5{\mu}Sv$로 나타났다. 분배실의 분배창을 기준으로 오른쪽 사방향에서 공간선량률이 높게 나타났다. 따라서 방사성의약품을 분배실에서 분배할 경우 방사선 작업종사자의 머무르는 시간을 짧게 해야 하며, 분배창의 오른쪽 사방향의 경우 피폭을 줄이기 위한 분배창의 설계가 필요하며, IV시 작업종사자의 개인피폭선량을 줄이기 위한 최선의 노력이 필요하다고 사료된다.

• Asian Pacific Journal of Cancer Prevention
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• 제17권7호
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• pp.3465-3468
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• 2016

Background: Fluorodeoxyglucose ($^{18}FDG$) PET/CT imaging has become an important component of the management paradigm in oncology. However, the significant imparted radiation exposure is a matter of growing concern especially in younger populations who have better odds of survival. The aim of this study was to estimate the effective dose received by patients having whole body $^{18}F$-FDG PET/CT scanning as per recent dose reducing guidelines at a tertiary care hospital. Materials and Methods: This prospective study covered 63 patients with different cancers who were referred for PET/CT study for various indications. Patients were prepared as per departmental protocol and 18FDG was injected at 3 MBq/Kg and a low dose, non-enhanced CT protocol (LD-NECT) was used. Diagnostic CT studies of specific regions were subsequently performed if required. Effective dose imparted by 18FDG (internal exposure) was calculated by using multiplying injected dose in MBq with coefficient $1.9{\times}10^{-2}mSv/MBq$ according to ICRP publication 106. Effective dose imparted by CT was calculated by multiplying DLP (mGy.cm) with ICRP conversion coefficient "k" 0.015 [mSv / (mG. cm)]. Results: Mean age of patients was $49{\pm}18$ years with a male to female ratio of 35:28 (56%:44%). Median dose of 18FDG given was 194 MBq (range: 139-293). Median CTDIvol was 3.25 (2.4-6.2) and median DLP was 334.95 (246.70 - 576.70). Estimated median effective dose imparted by $^{18}FDG$ was 3.69 mSv (range: 2.85-5.57). Similarly the estimated median effective dose by low dose (non-diagnostic) CT examination was 4.93 mSv (range: 2.14 -10.49). Median total effective dose by whole body 18FDG PET plus low dose non-diagnostic CT study was 8.85 mSv (range: 5.56-13.00). Conclusions: We conclude that the median effective dose from a whole body 18FDG PET/CT in our patients was significantly low. We suggest adhering to recently published dose reducing strategies, use of ToF scanner with CT dose reducing option to achieve the lower if not the lowest effective dose. This would certainly reduce the risk of second primary malignancy in younger patients with higher odds of cure from first primary cancer.

• 대한치과보철학회지
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• 제50권3호
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• pp.184-190
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• 2012

연구 목적: 이 연구는 상악 전치부와 하악 구치부 치근단 방사선촬영시 이동형 구내방사선촬영기와 벽걸이 구내방사선촬영기로 촬영한 경우에서 환자의 방사선량을 알아보고자 하였다. 연구 재료 및 방법: 방사선량 측정은 선량 측정용 두경부 마네킨의 23부위에 열형광선량계 소자를 위치시키고 해당 치근단 방사선촬영을 하였다. 열형광선량계 판독기로 흡수선량을 구하였고 방사선 조사된 조직의 비율을 곱하여 방사선 가중선량을 구하였다. 국제방사선방호위원회에서 2007년에 공지한 조직 가중계수를 이용하여 각 방사선촬영의 유효선량을 구하였다. 결과: 환자의 흡수선량은 이동형 구내방사선촬영기로 촬영한 상악 전치부와 이동형 및 벽걸이 구내방사선촬영기로 촬영한 하악 구치부 치근단방사선촬영의 경우 하악체에서 가장 높았다. 유효선량은 상악 전치부 치근단 방사선촬영에서는 이동형 촬영기로 촬영한 경우 $4{\mu}Sv$, 벽걸이 촬영기로 촬영한 경우 $2{\mu}Sv$였고 우측 하악 구치부 치근단 방사선촬영에서는 각각 $6{\mu}Sv$, $2{\mu}Sv$였다. 결론: 벽걸이 구내방사선촬영기보다 이동형 구내방사선촬영기로 촬영한 치근단 방사선촬영에서의 유효선량이 더 많기 때문에 술자는 구내방사선촬영기에 따른 방사선 노출 정도를 충분히 인지하고 이를 사용하여야 한다.

• 한국방사선학회논문지
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• 제5권6호
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• pp.415-420
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• 2011

본 연구는 방사선 일반 촬영시 촬영 도움자가 피폭받을 수 있는 테이블 주변의 산란선에 의한 피폭선량을 알아보고자 하였다. 두개부, 흉부, 복부, 요추부, 고관절, 그리고 슬관절 촬영시 테이블 중앙으로부터 옆으로 45cm, 75cm 떨어진 지점에서 바닥으로부터 70cm, 80cm, 130cm, 150cm 높이에서 산란선에 의한 피폭선량을 측정하였다. 측정결과 요추 측방향, 복부 정면, 그리고 고관절 촬영이 80cm 높이에서 $66.21{\mu}Sv$, $34.22{\mu}Sv$와 $32.35{\mu}Sv$로 가장 높은 피폭을 보였고, 흉부, 복부, 고관절, 두개부, 슬관절 순서로 선량이 감소하였다. 촬영 테이블 높이는 70cm 보다 80cm에서 대체로 높은 선량을 보였으며, 80cm 이상에서는 높이가 높아질수록 선량은 감소하였다. 측정된 선량들은 촬영 도움자가 납 방호복을 착용할 경우 일반인 연간 피폭선량한도인 1mSv와는 큰 차이가 있어 우려할 선량은 아닌 것으로 나타났다.

• 대한방사선기술학회지:방사선기술과학
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• 제39권2호
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• pp.237-246
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• 2016

방사성동위원소 사용시설 내/외 화장실 표면 방사선량률과 공간 방사선량률을 측정하여 화장실을 이용하는 환자 이외 방사선작업종사자 및 환자보호자 등의 안전성을 확보하고 방사선 방어 연구에 대한 기초 자료로 제시 하고자 한다. 2014년 5월 1일부터 7월 31일까지 인천광역시 소재 종합병원 방사성동위원소 사용시설 내/외 화장실 4곳의 공간 방사선량률과 작업 전/후 표면 방사선량률을 각각 측정하였다. 의료기관별 방사성동위원소 사용시설 내 화장실 이용 실태조사 결과 환자뿐만 아니라 환자 보호자, 일부 방사선 작업종사자까지 다양하게 이용하고 있었다. 화장실 내 공간 방사선량률 측정 결과 핵의학적 검사 중 감마촬영실을 이용하는 화장실의 누적 공간선량률은 8.86 mSv/hr으로 가장 높게 측정되었고, 방사성옥소 치료실 화장실은 7.31 mSv/hr, PET촬영실 화장실 2.29 mSv/hr, 외래 진료과 화장실 0.26 mSv/hr으로 각각 측정되었다. 방사성동위원소 작업 전/후 화장실 내 표면 방사선량률을 측정한 결과 대부분 환자 배설물이 직접 닫는 변기 앞에서 표면 방사선량률이 가장 높게 측정되었고, 화장실 내 중앙, 입구 순으로 측정되었다. 개봉선원은 물리적 반감기가 짧고 에너지가 낮아 비교적 안전하여 방사선 관리구역에서 안전하게 사용되고 있다. 그러나 저에너지 이며 짧은 반감기의 방사선원이라 하더라도 환자에게 투여되면 그 이후 환자는 움직이는 방사선원이 되며 환자가 이용하는 장소는 배설물에 의한 방사선 오염 장소가 된다. 따라서 효과적으로 유효선량을 최소화하고 불필요한 피폭선량을 줄이기 위해 방사성동위원소 투여 후 충분한 수분 섭취를 독려하여 생물학적 반감기를 낮추고, 물리적 반감기가 허용 선량이하로 될 때까지 주변인은 환자로부터 가급적 멀리 떨어져 생활하도록 권고되어야 한다.

• Imaging Science in Dentistry
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• 제42권2호
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• pp.65-70
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• 2012

Purpose : The aim of this study was to compare the effective dose for imaging of mandible between multi-detector computed tomography (MDCT) and cone-beam computed tomography (CBCT). An MDCT with low dose technique was also compared with them. Materials and Methods : Thermoluminescent dosimeter (TLD) chips were placed at 25 organ sites of an anthropomorphic phantom. The mandible of the phantom was exposed using 2 different types of MDCT units (Somatom Sensation 10 for standard-dose MDCT, Somatom Emotion 6 for low-dose MDCT) and 3 different CBCT units (AZ3000CT, Implagraphy, and Kavo 3D eXaM). The radiation absorbed dose was measured and the effective dose was calculated according to the ICRP 2007 report. Results : The effective dose was the highest for Somatom Sensation 10 (425.84 ${\mu}Sv$), followed by AZ3000CT (332.4 ${\mu}Sv$), Somatom Emotion 6 (199.38 ${\mu}Sv$), and 3D eXaM (111.6 ${\mu}Sv$); it was the lowest for Implagraphy (83.09 ${\mu}Sv$). The CBCT showed significant variation in dose level with different device. Conclusion : The effective doses of MDCTs were not significantly different from those of CBCTs for imaging of mandible. The effective dose of MDCT could be markedly decreased by using the low-dose technique.

• 한국산업보건학회지
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• 제28권3호
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• pp.283-291
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• 2018

Objectives: To monitor the radon concentration level in plants that handle phosphorus rock and produce gypsum board and cement, and evaluate the effective dose considering the effect of radon exposure on the human body. Methods: Airborne radon concentrations were measured using alpha-track radon detectors (${\alpha}$-track, Rn-tech Co., Korea) and continuous monitors (Radon Sentinel 1030, Sun Nuclear Co., USA). Radon concentrations in the air were converted to radon doses using the following equation to evaluate the human effects due to radon. H (mSv/yr) = Radon gas concentration x Equilibrium factor x Occupancy factor x Dose conversion factor. The International Commission on Radiological Protection (ICRP) used $8nSv/(Bq{\cdot}hr/m^3)$ as the dose conversion factor in 2010, but raised it by a factor of four to $33nSv/(Bq{\cdot}hr/m^3)$ in 2017. Results: Radon concentrations and effective doses in fertilizer manufacturing process averaged $14.3(2.7)Bq/m^3$ ($2.0-551.3Bq/m^3$), 0.11-0.54 m㏜/yr depending on the advisory authority and recommendation year, respectively. Radon concentrations in the gypsum-board manufacturing process averaged $14.9Bq/m^3$ at material storage, $11.4Bq/m^3$ at burnability, $8.1Bq/m^3$ at mixing, $10.0Bq/m^3$ at forming, $8.9Bq/m^3$ at drying, $14.7Bq/m^3$ at cutting, and $10.5Bq/m^3$ at shipment. It was low because it did not use phosphate gypsum. Radon concentrations and effective doses in the cement manufacturing process were $23.2Bq/m^3$ in the stowage area, $20.2Bq/m^3$ in the hopper, $16.8Bq/m^3$ in the feeder and $11.9Bq/m^3$ in the cement mill, marking 0.12-0.63 m㏜/yr, respectively. Conclusions: Workers handling phosphorous gypsum directly or indirectly can be assessed as exposed to an annual average radon dose of 0.16 to 2.04 mSv or 0.010 to 0.102 WLM (Working Level Month).