• Title/Summary/Keyword: 방사선 피폭관리

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Leakage and Scattered Radiation from X-ray Unit in Radiography (영상의학과 엑스선 발생장치의 누설 및 산란선량 측정)

  • Im, In-Chul;Lee, Jae-Seung;Kweon, Dae-Cheol
    • Journal of the Korean Society of Radiology
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    • v.5 no.3
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    • pp.155-159
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    • 2011
  • The purposed of this study were measured the radiation exposure of patients and workers by generators, and the protection state for radiation facilities. The subject of the study by X-ray generators in university hospitals of capital area, we measured the maximum irradiation condition of 80 kVp, 200 mA, 0.1 second in the control entrance, control room window, entrance of radiography, adjacent site. The leakage dose per week was which the control entrance was 0.11 mR/week, control room window was 0.15 mR/week, entrance of radiography was 0.12 mR/week and adjacent site was 0.06 mR/week with X-ray unit the mean And the leakage mean dose was 0.11 mR/week. Diagnostic X-ray tubes must ensure that the leakage radiation in the maximum leakage dose in week emitted by the tube outside the useful beam does not exceed certain levels provided by standards.

General Radiography Imaging Usage and Effective Dose of Inpatients: Based on Data from Inpatients in 2018 (입원환자 일반촬영 이용량 및 피폭선량: 2018년 입원환자데이터)

  • Jong-Won Gil
    • Journal of radiological science and technology
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    • v.47 no.2
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    • pp.107-116
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    • 2024
  • In this study, we analyzed the use of general radiography imaging and effective dose in inpatients. Our aim is to help reduce national medical radiation exposure doses and develop rational health-care financial policies. The effective dose for each general radiography was calculated using the ALARA-GR program for 53 types (total: 260 codes) general radiography codes selected from 'National Health Insurance Care Benefit Cost'. The usage of general radiography was analyzed in the 2018 inpatient patient data of the Health Insurance Review and Assessment Service, and the effective dose for each general radiography was analyzed. 89.00% of inpatients undergo general radiography imaging at least once, with an average of 12.63 scans per person and an effective dose of 1.00 mSv. Those who received support from Medical Aid showed a higher value compared to those who were insured by National Health Insurance, with 17.39 cases and 1.43 mSv (p<.001). Chest had the highest usage rate at 23.12% for general radiography imaging, while L-spine had the highest effective dose at 24.53%. It is estimated that 420 inpatients patients undergo 121 to 820 general radiography imaging procedures per year, and 233 inpatients are estimated to have an annual effective dose of >20.00~58.25 mSv. Rational use of health-care finances and the practice of medical radiation safety management are essential for the well-being of individuals, the enhancement of quality of life, and the improvement of health-care quality.

The Consideration of nuclear medicine technologist's occupational dose from patient who are undergoing 18F-FDG Whole body PET/CT : Aspect of specific characteristic of patient and contact time with patient (18F-FDG Whole Body PET/CT 수검자의 거리별 선량 변화에 따른 방사선 작업종사자의 유효선량 고찰: 환자 고유특성 및 응대시간 측면)

  • Kim, Sunghwan;Ryu, Jaekwang;Ko, Hyunsoo
    • The Korean Journal of Nuclear Medicine Technology
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    • v.22 no.1
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    • pp.67-75
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    • 2018
  • Purpose The purpose of this study is to investigate and analyze the external dose rates of $^{18}F-FDG$ Whole Body PET/CT patients by distance, and to identify the main factors that contribute to the reduction of radiation dose by checking the cumulative doses of nuclear medicine technologist(NMT). Materials and Methods After completion of the $^{18}F-FDG$ Whole Body PET/CT scan($75.4{\pm}3.3min$), the external dose rates of 106 patients were measured at a distance of 0, 10, 30, 50, and 100 cm from the chest. Gender, age, BMI(Body Mass Index), fasting time, diabetes mellitus, radiopharmaceutical injection information, creatine value were collected to analyze individual factors that could affect external dose rates from a patient's perspective. From the perspective of NMT, personal pocket dosimeters were worn on the chest to record accumulated dose of NMT who performed the injection task($T_1$, $T_2$ and $T_3$) and scan task($T_4$, $T_5$ and $T_6$). In addition, patient contact time with NMT was measured and analyzed. Results External dose rates from the patient for each distance were calculated as $246.9{\pm}37.6$, $129.9{\pm}16.7$, $61.2{\pm}9.1$, $34.4{\pm}5.9$, and $13.1{\pm}2.4{\mu}Sv/hr$ respectively. On the patient's aspect, there was a significant difference in the proximity of gender, BMI, Injection dose and creatine value, but the difference decreased as the distance increased. In case of dialysis patient, external dose rates for each distance were exceptionally higher than other patients. On the NMT aspect, the doses received from patients were 0.70, 1.09, $0.55{\mu}Sv/person$ for performing the injection task($T_1$, $T_2$, and $T_3$), and were 1.25, 0.82, $1.23{\mu}Sv/person$ for performing the scan task($T_4$, $T_5$, $T_6$). Conclusion we found that maintaining proper distance with patient and reducing contact time with patient had a significant effect on accumulated doses. Considering those points, efforts such as sufficient water intake and encourage of urination, maintaining the proper distance between the NMT and the patient(at least 100 cm), and reducing the contact time should be done for reducing dose rates not only patient but also NMT.

Comparison of ESD and Major Organ Absorbed Doses of 5-Year-Old Standard Guidelines and Clinical Exposure Conditions (소아 5세 표준촬영 가이드라인과 임상 촬영조건의 입사표면선량과 주요 장기흡수선량 비교)

  • Kang, A-Rum;Lee, In-Ja;Ahn, Sung-Min
    • Journal of radiological science and technology
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    • v.40 no.3
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    • pp.355-361
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    • 2017
  • Pediatrics are more sensibility to radiation than adults and because they are organs that are not completely grown, they have a life expectancy that can be adversely affected by exposure. Therefore, the management of exposure dose is more important than the case of adult. The purpose of this study was to determine the suitability of the 10 year old phantom for the 5 year old pediatric's recommendation and the incident surface dose, and to measure the organ absorbed dose. This study is compared the organ absorbed dose and the entrance surface dose in the clinical conditions at 5 and 10 years old pediatric. Clinical 5 year old condition was slightly higher than recommendation condition and 10 year old condition was very high. In addition, recommendation condition ESD was found to be 43% higher than the ESD of the 5 year old group and the ESD of the 10 year old group was 126% higher than that of the 5 year old group. The recommended ESD at 5 years old and the ESD according to clinical imaging conditions were 31.6%. There was no significant difference between the 5 year old recommended exposure conditions and the organ absorbed dose due to clinical exposure conditions, but there was a large difference between the Chest and Pelvic. However, it was found that there was a remarkable difference when comparing the organ absorbed dose by 10 year clinical exposure conditions. Therefore, more detailed standard exposure dose for the recommended dose of pediatric should be studied.

Correlation Analysis of between Patient and Equipment Factors and Radiation Dose in Chest Low Dose and Abdominal Non-contrast CT (흉부 저선량 및 복부 비조영 CT 검사에서 환자 및 장비 인자와 선량과의 상관관계 분석)

  • Shim, Jina;Lee, Youngjin
    • Journal of the Korean Society of Radiology
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    • v.15 no.2
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    • pp.117-123
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    • 2021
  • This paper is to establish a basis for a dose reduction strategy by confirming correlations with the factors that may affect the radiation dose based on the dose records in low-dose chest CT and abdominal non-contrast CT. In order to find out the causes of unnecessary exposure, the correlation between seven factors (age, gender, height, weight, BMI, patient status [inpatient and outpatient], and use of dose modulation) and CT dose were identified. Logistic regression was used as the statistical analysis for correlation verification. In the low dose chest CT, as the higher values of height and BMI and dose modulation off were associated with lowering the risk exceeding Diagnostic Reference Levels(DRL) (odds ration<1, p<0.05). However, as woman compared to man and the higher values of weight were associated with highering the risk exceeding DRL (odds ration>1, p<0.05). In the abdomen CT, as dose modulation off were associated with lowering the risk exceeding DRL (odds ration<1, p<0.05). Therefore It is necessary to conduct research on the relationship between various factors affecting radiation exposure and patient radiation dose for reducing the dose.

Preliminary Assessment of Radiological Impact on the Domestic Railroad Transport of High Level Radioactive Waste (고준위 방사성폐기물의 국내철도운반에 관한 방사선영향 예비평가)

  • Seo, Myunghwan;Dho, Ho-Seog;Hong, Sung-Wook;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.4
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    • pp.381-390
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    • 2017
  • In Korea, commercial nuclear power plants and research reactors have on-site storage systems for the spent nuclear fuel, but it is difficult to expand the facilities used for the storage systems. If decommissioning of nuclear power plants starts, an amount of high level radioactive waste will be generated. In this study, a radiological impact assessment of the railroad transport of high level radioactive waste was carried out considering radiation workers and the public, using the developed transport container as the transport package. The dose rates for workers and the public during the transport period were estimated, considering anticipated transport scenarios, and the results compared with the regulatory limit. A sensitivity analysis was also carried out by considering the different release ratios of the radioactive materials in the high level radioactive waste, and different distances between the transport container and workers during loading and unloading phases and while attaching another freight car. For all the anticipated transport scenarios, the radiological impacts for workers and the public met the regulatory limits.

Evaluation of Spatial Dose Rate in Working Environment during Non-Destructive Testing using Radioactive Isotopes (방사성동위원소를 이용한 비파괴 검사 시 작업환경 내 공간선량률 평가)

  • Cho, Yong-In;Kim, Jung-Hoon;Bae, Sang-Il
    • Journal of the Korean Society of Radiology
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    • v.16 no.4
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    • pp.373-379
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    • 2022
  • The radiation source used for non-destructive testing have permeability and cause a scattered radiation through collisions of surrounding materials, which causes changes in the surrounding spatial dose. Therefore, this study attempted to evaluate and analyze the distribution of spatial dose by source in the working environment during the non-destructive test using monte carlo simulation. In this study, Using FLUKA, a simulation code, simulates 60Co, 192Ir, and 75Se source used in non-destructive testing, The reliability of the source term was secured by comparing the calculated dose rate with the data of the Health and Physics Association. After that, a non-destructive test in the radiation safety facility(RT-room) was designed to evaluate the spatial dose according to the distance from the source. As a result of the spatial dose evaluation, 75Se source showed the lowest dose distribution in the frontal position and 60Co source showed a dose rate of about 15 times higher than that of 75Se and about 2 times higher than that of 192Ir. In addition, the spatial dose according to the distance tends to decrease according to the distance inverse square law as the distance from the source increases. Exceptionally, 60Co, 192Ir, and 75Se sources confirmed a slight increase within 2 m of position. Based on the results of this study, it is believed that it will be used as supplementary data for safety management of workers in radiation safety facilities during non-destructive testing using radioactive isotopes.

The Effects of Cynanchi wilfordii Radix Ethanol Extracts upon Irradiated Rat's Blood and Organ (백하수오 에탄올추출물이 방사선조사에 따른 흰쥐의 혈구 및 장기에 미치는 영향)

  • Kim, Jang-Oh;Choi, Jun-Hyeok;Shin, Ji-Hye;Jung, Do-Young;Min, Byung-In
    • Journal of radiological science and technology
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    • v.39 no.3
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    • pp.451-459
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    • 2016
  • The development of radioprotector is being actively conducted in order to reduce the damage from over radiation exposure at radiation accident or radiation therapy. So this study was confirmed for radiation protective effects using the Cynanchi wilfordii Radix that has been known to be effective for antioxidant activity, anti-cancer, immune enhancing effects. The method of this study was administered orally Cynanchi wilfordii Radix ethanol extracts to Sprague Dawley Rat(SD Rat) for 14 days once a day, while measuring changed blood cell, spleen index, liver and uterus tissue along the change in time of 1, 4, 7 and 21 days after X-ray beam of 7 Gy irradiation. As the result of the experiment, the experimental group's rats which are administered with Cynanchi Wilfordii Radix ethanol extracts showed a rapid recovery in white blood cell count(p < 0.05) and spleen index(p < 0.05). In addition, condensation of nuclei, cytoplasmic swelling, and inflammatory cell infiltration in experimental group's liver cell was decreased more than in irradiation group's component. Further, experimental group's Uterine gland decreased the apoptosis more than irradiation group's components did. It is expected that Cynanchi Wilfordii Radix extracts will be useful as a new radioprotector. With above in mind, this paper may provide appropriate implications with the field of emergency management such as radiation accident.

액체폐기물 처리계통 고선량 폐필터 장기저장설비

  • Lee, Sang-Tae;An, Won-Seok;Mun, Cheol-Ung;Lee, Eun-Hak;Im, Wan-Seok
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2007.05a
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    • pp.65-66
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    • 2007
  • 원자력 발전소 방사선 관리구역 1차 계통수의 수질 정화 후 발생된 고선량 폐필터를 방사능 붕괴 후 잡고체 폐기물로 처리하기 위한 장기저장시설 내 설치 될 설비 임. 동 설비는 자동화공정을 기본으로 한정된 공간에 다량의 폐필터를 가장 효율적으로 저장 할 수 있는 최적의 설비이며, 폐필터 장입, 인출 시 작업시간단축, 작업자 피폭저감, 오염확산 방지는 물론 폐기물을 감용시켜 폐기물처리, 처분 비용 절감에 기여하고자 한다.

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원전 출력감발 운전에 따른 방사성 부식생성물 거동 분석

  • 성기방
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11a
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    • pp.103-109
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    • 1996
  • 고리 원자력 1호기 14주기(‘95년도) 운전기간 중 증기발생기 세관 열전달 용량 저하로 전출력 운전 기간동안 정격출력보다 15% 감발 운전한 경험이 있었는데, 이 기간중 냉각재내 방사성 부식생성물(CRUD) 농도가 약 80% 감소됨을 발견하였다. 이때 출력감소 비율보다 많은 CRUD 감소현상 규명을 위해 냉각재 수질관리인자와 EPRI 피복재 부식모델인 PFCC코드를 사용한 피 복재 산화물 두께변화 등을 비교한 결과, 운전중 용출되는 방사성 부식생성물은 핵연료 표면의 피복재 산화물에 흡착된 Co핵종이 피복재 산화물 이탈시 함께 거동하는 것으로 확인되었으며, 피복재 산화물 이탈은 산화막 두께 및 열유속에 주로 의존함이 밝혀졌다. 따라서 냉각재내에서 방사성 부식 생성물의 생성률 저감을 위해서는 정상운전시 핵연료 표면의 산화막 증가를 억제할 수 있는 수질 조건을 도출하고 그에따른 운전을 통해 원전 작업자의 방사선 피폭량 저감 및 방사성폐기물의 발생을 줄일 수 있을 것으로 여겨진다.

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