• Title/Summary/Keyword: 외부피폭

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Changes in External Radiation Dose Rate for PET-CT Test Patients (PET-CT 검사 환자의 외부 방사선량률 변화)

  • Kim, Su-Jin;Han, Eun-Ok
    • Journal of Radiation Protection and Research
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    • v.37 no.2
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    • pp.103-107
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    • 2012
  • This paper analyzes changes in the external radiation dose rate of PET-CT test patients as a part of providing basic materials for reduction of radiation exposure to PET-CT test patients. In theory the measurement of external radiation dose rate of PET-CT test patients shows that the further the distance from the patient injected with radioactive pharmaceutical and a longer time elapsement from the injection leads to a smaller amount of radiation. Particularly, the amount of radiation marked the highest in the chest was at 4.17 minutes immediately after the intravenous injection and in the head after 77.47 minutes after urination in advance to the PET-CT test. As in the generalized information, it is desired to keep distance between the patient and caretakers or professionals to reduce the amount of radiation exposure from PET-CT test patients and to resume contact the patient after the time when the radiation has reduced. If contact is unavoidable, it is desired to keep at least 200cm from the patient. In addition, the amount of radiation reached the highest in the chest at first and then in the head from 77 minutes after injection. Accordingly, it would be helpful in achieving the optimization if contact is made based on the patient's physical characteristics. This study is significant as it measures changes in radiation the dose rate by; distance from the PET-CT test patient, time elapsed, and specific parts of body. Further studies based on the findings in this paper are required to analyze changes in radiation dose rate in accordance with individual characteristics unique to PET-CT patients and to utilize the results to reduce the amount of radiation patient, caretakers and professions are exposed.

Radiation Exposure of Hands and Feet from $^{18}F$-FDG in Radio-technologists (방사선 작업 종사자의 작업화 및 작업복의 방사선 오염 분석)

  • Lee, Seung-Jae;Jeong, Seok;Seo, Soo-Hyun;Park, Yong-Sung;Park, Hoon-Hee;Oh, Shin-Hyun;Lim, Han-Sang;Kim, Jae-Sam;Lee, Chang-Ho
    • The Korean Journal of Nuclear Medicine Technology
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    • v.15 no.2
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    • pp.94-98
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    • 2011
  • Purpose: The radiation exposure from radioisotope at the hands and foots of radiation workers who works in PET/CT part at the department of nuclear medicine was investigated in this study. Materials and Methods: From 4th August 2010 to 14th January 2011, 6 radio-technologists' radiation on hands and feet were measured. All radio-technologist have been examined around 8; morning, 12; afternoon, and 16 o'clock; evening, respectively. SPSS version 17 was used for statistical analysis. Results: The statistical significances were calculated in several ways. The radiation from both hands and feet in the Morning was lower than Afternoon and Evening. In some cases, the detected radiation showed extremely high values in data. In order to find the effect of the ${\gamma}$-ray on the hand, the estimated doses were presumably calculated, however, the exposure dose on feet were unmeasured. Conclusion: Even if the radiation exposure from the radioisotope at the hands and feet were under the limitations, it is definitely needs to prevent the radiation-contamination. Therefore, the radio-technologists need to have a proper radiation-dealing-procedure of their own, and must try to prevent a radiation exposure by themselves.

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Evaluation Absorbed Dose During the Breast Cancer Brachytherapy in Canine Phantom (반려견 팬텀에서 유방암 근접방사선치료 시 흡수선량 평가)

  • Kim, Jung-Hoon;Lee, Deuk-Hee
    • Journal of the Korean Society of Radiology
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    • v.14 no.5
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    • pp.523-528
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    • 2020
  • The application of breast cancer, which has the highest incidence in females among cancer that is the number one cause of death for dogs, was to be evaluated the absorbed dose during brachytherapy using simulation. MCNPX program was used for simulation, and a small size canine phantom was produced to measure absorbed dose. The results of the absorbed dose was the highest at 192Ir to 1.02E-12 Gy/# for tumors, and the same tendency was shown for internal and external absorbed dose. Therefore, the selection of appropriate sources for dog breast cancer should be considered in brachytherapy, taking into account dog breeds and exposures.

양성자 빔을 이용한 의료용 방사성동위원소 C-11과 Tc-99m 개발

  • Kim, Jae-Hong;Lee, Ji-Seop;Park, Hyeong;Jeon, Gwon-Su
    • Proceedings of the Korean Vacuum Society Conference
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    • 2011.02a
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    • pp.235-235
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    • 2011
  • 진단용 또는 의료용 동위원소들은 안정한 표적물질에 높은 에너지의 양성자가 조사 될 때 핵반응에 의해서 생성된다. 양성자를 충분한 에너지로 가속하기 위해서 이용되는 사이클로트론의 주요 부분은 (1) 진공시스템, (2) 자석시스템, (3) RF 시스템, (4) 외부 이온원, (5) 수직 축 방향빔의 수평방향 전환 시스템, (6) 빔 인출 장치, 그리고 빔전송과 표적장치로 구성된다. 인출된 빔은 표적까지 손실 없이 전송 될 수 있도록 빔 라인에 설치된 광학적 요소에 의해 집속되어 전송된다. 방사성동위원소의 생산량은 양성자 빔의 특성과 표적 물질의 종류에 따라 결정된다. 즉, 표적 물질에 조사하는 입자의 종류, 적절한 핵반응 선택, 최소량의 불순핵종과 원하는 방사핵종의 최대수율을 얻을 수 있는 최적 에너지 범위결정, 표적 물질의 냉각능력과 입자전류의 세기 등을 고려 하여야 한다. 동위원소 생산에 있어서 예측되는 수율은 입자전류와 비례하며, 에너지에 대한 핵반응 단면적 즉, 여기함수를 적분하여 아래와 같이 얻을 수 있다. 주 생성핵종의 생산 효율을 최대로 높이고 불순 핵종의 생성량을 최소로 감소시키기 위해서는 정확한 여기 함수 자료를 바탕으로 최적 입자를 결정하여야 한다. 또한 이론적인 생산 수율은 입자 전류에 정비례하지만, 입자 전류가 클경우 생산수율은 이론적인 수율보다 적다. 입자빔의 불균일성, 표적의 방사선 피폭에 의한 손상, 높은 입자전류에 의해 발생하는 열로 인하여 생성 핵종이 증발하여 생산 수율이 감소된다. 본 발표에서 방사핵종 C-11과 Tc-99m을 개발하기 위한 최적 조건에 관한 연구결과를 보고하고자 한다.

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Modification of Trunk Thickness of MIRD phantom Based on the Comparison of Organ Doses with Voxel Phantom (체적소팬텀과의 장기선량 비교를 통한 MIRD팬텀 몸통두께 수정)

  • Lee, Choon-Sik;Park, Sang-Hyun;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.199-206
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    • 2003
  • Because the MIRD phantom, the representative mathematical phantom was developed for the calculation of internal radiation dose, and simulated by the simplified mathematical equations for rapid computation, the appropriateness of application to external dose calculation and the closeness to real human body should be justified. This study was intended to modify the MIRD phantom according to the comparison of the organ absorbed doses in the two phantoms exposed to monoenergetic broad parallel photon beams of the energy between 0.05 MeV and 10 MeV. The organ absorbed doses of the MIRD phantom and the Zubal yokel phantom were calculated for AP and PA geometries by MCNP4C, general-purpose Monte Carlo code. The MIRD phantom received higher doses than the Zubal phantom for both AP and PA geometries. Effective dose in PA geometry for 0.05 MeV photon beams showed the difference up to 50%. Anatomical axial views of the two phantoms revealed the thinner trunk thickness of the MIRD phantom than that of the Zubal phantom. To find out the optimal thickness of trunk, the difference of effective doses for 0.5 MeV photon beams for various trunk thickness of the MIRD phantom from 20 cm to 36 cm were compared. The optimal thunk thickness, 24 cm and 28 cm for AP and PA geometries, respectively, showed the minimum difference of effective doses between the two phantoms. The trunk model of the MIRD phantom was modified and the organ doses were recalculated using the modified MIRD phantom. The differences of effective dose for AP and PA geometries reduced to 7.3% and the overestimation of organ doses decreased, too. Because MIRD-type phantoms are easier to be adopted in Monte Carlo calculations and to standardize, the modifications of the MIRD phantom allow us to hold the advantage of MIRD-type phantoms over a voxel phantom and alleviate the anatomical difference and consequent disagreement in dose calculation.

[ 137Cs] and 40K Activities of Foodstuffs Consumed in Jeju (제주지역에서 소비되는 식품 중 137Cs과 40K 방사능 농도)

  • Kang, Tae-Woo;Hong, Kyung-Ae;Park, Won-Pyo;U., Zang-Kual
    • Korean Journal of Environmental Agriculture
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    • v.23 no.1
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    • pp.52-58
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    • 2004
  • This work was conducted to provide the reference data of radioactivity in the foodstuffs at a radiological emergency situation in Jeju Island The sampled foodstuffs were agricultural (31), livestock (6), marine (12) and forest products (4), and processed foods (3) consumed by Jeju Islanders. $^{137}Cs$ and $^{40}K$ activities were determined by HPGe r-ray spectromety. The activity ranges of $^{137}Cs$ was ${\sim}650\;mBq/kg$ fresh in the agricultural products, ${\sim}131\;mBq/kg$. fresh in the livestock, ${\sim}834\;mBq/kg$ fresh in the forest, ${\sim}253\;mBq/kg$ fresh in the marine and $32.0{\sim}483\;mBq/kg$. fresh in the processed foods (tea). In case of $^{40}K$ the activity was $16.6{\sim}542\;Bq/kg$. fresh in the agricultural products, $39.1{\sim}294\;Bq/kg$ fresh in the livestock, $85.5{\sim}116\;Bq/kg$ fresh in the forest, $50.1{\sim}657\;Bq/kg$ fresh in the marine, and $33.6{\sim}1,065\;Bq/kg$ fresh in the processed foods (tea). The highest activity of $^{137}Cs$, 834mBq/kg fresh was observed in oak mushroom and $^{40}K$ 1,065 Bq/kg fresh in coffee. Annual effective doses of $^{137}Cs$ and $^{40}K$ by intake of foodstuffs per capita were the following order; agricultural products (66,543 nSv) > livestock products (19,311 nSv) > processed foods (6,648 nSv) > marine products (6,579 nSv) > forest products (860 nSv). Therefore, total annual effective dose was summed 99,941 nSv which is quite low level comparing to the annual effective dose by external exposure, 2,400,000 nSv. The data obtained in this study can be useful for monitoring whether the foodstuffs are contaminated or not at an emergency radiation accident, and showed that the foodstuffs consumed in Jeju are safe in terms of annual effective dose of $^{137}Cs$ and $^{40}K$

Observation on The Frequency of Chromosomal Aberration and Changes in Number of Peripheral Lymphocytes in Radioactive Iodine Treatment (방사성옥소 투여에 따른 말초혈액 림프구 수의 변화 및 염색체이상 빈도의 관찰)

  • Koo, Chun-Hee;Shin, Min-Ho;Park, Young-Ju;Lee, Jung-Yim;Park, Tae-Yong;Lee, Jae-Yong;Kim, Chong-Soon;Han, Seung-Soo;Kim, Kwang-Hoe;Kim, Hee-Geun;Kang, Duck-Won;Song, Myung-Jae
    • The Korean Journal of Nuclear Medicine
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    • v.29 no.3
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    • pp.343-349
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    • 1995
  • Background : For biological dosimetry of radiation exposure, both observing hematologic change and calculating Ydr by chromosomal analysis as biological indicators are widely used. However, due to the lack of studies on biological dosimetry of radiation dose absorbed in the body such as in the cases of radioactive iodine therapy, the maximal and safe dose is not well known, nor is the extent to which the body can safely endure radiation exposure. Purpose : To investegate the practical applicability of hematologic changes and Ydr as an indicator for estimating radiation exposure, to patients with thyroid diseases after doses of radioactive iodine. Material and Methods : 5 patients with hyperthyroidism and 35 patients who have had thyroid cancer operation were under treatment with radioactive iodine, changes in number of lymphocytes were tracked and Ydr was calculated for more than 2 months by chromosomal analysis in peripheral lymphocytes. Results ; 1) The number of lymphocytes began to decrease 2 weeks after doses of radioactive iodine, and reached the nadir after 6 and 8 weeks, then gradually recovered. 2) The nadir count of lymphocytes was reversely correlated with the administered dosage of radioactive iodine. 3) Ydr was generally stable between 2 and 8 weeks. 4) The maximal value of Ydr was correlated with the administered dosage of radioactive iodine. 5) Ydr value at the 2nd week increased with augmented dosage of radioactive iodine. 6) Ydr value at the 2nd week was correlated with fall of lymphocyte count. Conclusion : Patients must be closely observed, because temporary bone marrow suppression and slight chromosomal aberration can be produced by even generally used dosages of radioactive iodine for diagnosis and therapy. Maximal percent fall of lymphocyte count, Ydr at the 2 week interval and maximal Ydr can be used as the biological predictor of administered dosage of radioactive iodine.

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Measurement from Moving Vehicle Health Screening Outside of The Leakage Dose (이동건강검진차량에서 외부의 누설선량 측정)

  • Han, Beom-Hee;Han, Sang-Hyun;Mo, Eun-Hee;Kim, Chong-Yeal
    • The Journal of the Korea Contents Association
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    • v.15 no.3
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    • pp.192-198
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    • 2015
  • Checked out by the moving vehicle health checks for patients, practitioners, and the increase in radiation dose outside the vehicle, but an investigation into the leakage of radiation can still be negligible. In this study, through experimental results were as follows: Dose that occurs most often where the leak in the right door $1.14{\pm}1.75mR/h$, X-ray generator in terms of proximity to the top $0.65{\pm}1.25mR/h$, X-ray generator and away to the bottom in terms $0.91{\pm}1.25mR/h$, the adjacent rear detector in the upper part $96.98{\pm}158.88mR/h$ dose of the leak appeared in various locations. By measuring position from the rear of the adjacent detector $67.48{\pm}97.03mR/h$ dose had the highest leakage into. Generating device for diagnosis of radiation safety regulations regarding the maximum leakage dose per week, but all met back when it is displayed in the leakage dose Hourly rates do not ignore the leakage radiation dose were measured. Therefore, a mobile health screening in a vehicle outside of the leakage radiation dose to the liver and move on we are not interested twelve barrier leakage radiation dose of defense has a chance to re-evaluate the standards required, and move the vehicle health check using the X-ray increases as the dose per hour, depending on the criteria for choosing the appropriate measures that will require effort.

Development of the Reference Korean Female Voxel Phantom (한국인 기준여성 체적소형 모의체 개발)

  • Ham, Bo-Kyoung;Cho, Kun-Woo;Yeom, Yoen-Soo;Jeong, Jong-Hwi;Kim, Chan-Hyeong;Han, Min-Cheol
    • Journal of Radiation Protection and Research
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    • v.37 no.1
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    • pp.41-49
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    • 2012
  • The objective of this study is for development of the reference Korean female phantom, HDRK-Woman. The phantom was constructed by adjusting a Korean woman voxel phantom to the Reference Korean data. The Korean woman phantom had been developed based on the high-resolution color slice images obtained from an adult Korean female cadaver. There were a total of 39 organs including the 27 organs specified in ICRP 103 for effective dose calculation. The voxel resolution of the phantom was $1.976{\times}1.976{\times}2.0619\;mm^3$ and the voxel array size is $261{\times}109{\times}825$ in the x, y and z directions. Then, the voxel resolution was changed to $2.0351{\times}2.0351{\times}2.0747\;mm^3$ for adjustment of the height and total bone mass of the phantom to the Reference Korean data. Finally, the internal organs and tissue were adjusted using in-house software program developed for 3D volume adjustment of the organs and tissue. The effective dose values of HDRK phantoms were calculated for broad parallel photon beams using MCNPX Monte Carlo code and compared with those of ICRP phantoms.

Characterization of Domestic Earthquake Events for the Safety Assessment of the Geological Disposal System (심지층 처분시스템의 안전성평가를 위한 국내 지진 발생 특성 평가)

  • Kim, Jung-Woo;Cho, Dong-Keun;Ko, Nak-Youl;Jeong, Jongtae
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.13 no.2
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    • pp.87-98
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    • 2015
  • Safety assessments of geological radioactive waste disposal systems, need to consider the abnormal scenario in which a system is impacted by external events in addition to a reference scenario. In this study, the characterization and prediction of an earthquake as an external event which will impact disposal systems were conducted probabilistically and statistically for the safety assessment. The domestic earthquake data were analyzed, and the prediction methodologies of the earthquake were suggested with a computational example. From the results, the earthquake occurrence rates in Korea ranged from 0.4 /yr to 36.2 /yr depending on the data set and the completeness magnitude. From a conservative point of view, the earthquake occurrence rate in the disposal system was suggested as 5.4×10-4 /yr considering the area of the disposal system. At that time, the completeness magnitude of an earthquake was 2.3. This study will be followed by an appraisal of impacts associated with external events on the geological disposal system, and it will contribute to improvements in reliability of the safety assessment.