• Title/Summary/Keyword: 피폭 선량

Search Result 1,157, Processing Time 0.034 seconds

A study on the Radiation exposure of simple abdomen x-ray in Radiography (복부 단순 X선검사시 피복 선량에 관한 연구)

  • Ko In Ho;Lee Kyung Sung;Shin Dong Yong
    • Journal of The Korean Radiological Technologist Association
    • /
    • v.27 no.2
    • /
    • pp.57-65
    • /
    • 2001
  • This study was performed to measure about exposure dose during simple abdomen x-ray Radiography. The exposure dose was measured by PDD, surface dose, percentage scatter dose, respectively. The result was as followed: 1. When tube voltage were increased wi

  • PDF

The evaluation of the radiation dose and the image quality during MDCT using Glass Rod Detector (유리선량계를 이용한 복부 MDCT 검사시 피폭선량 및 화질평가)

  • Kim, Chang-Gyu;Park, Byung-Sub
    • 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.

Evaluation of Dose Enhancement by Gold Nanoparticles using Mathematical Head Phantom (금 나노입자를 활용한 두부 모의피폭체에서의 선량증가 효과 평가)

  • Hwang, Chulhwan;Park, Eun-Tae;Kim, Jung-Hoon
    • The Journal of the Korea Contents Association
    • /
    • v.16 no.8
    • /
    • pp.477-483
    • /
    • 2016
  • The effect of dose enhancement was evaluated using Snyder head phantom, dependence on size of gold nanoparticle and material concentration in megavoltage X, ${\gamma}$-ray. Monte Carlo simulation using MCNPX was used for 4, 6, 10, 15 MV and Co-60 ${\gamma}$-ray. Described the tumor in Snyder head phantom, gold nanoparticle of 25, 75, 125nm diameter was inserted inside tumor. Concentration of dose enhancement material was used for 5, 15, 25 mg/g and dose enhancement factor was calculated on the basis of the no dose enhancement material. The lower incident energy and the higher concentration of material were that high dose enhancement factor is indicated. The size of gold nanoparticle had relatively high dependence on lower incident energy and higher concentration of material. It will increase dose inside the tumor, and be additional effect of use of gold nanoparticles in radiation therapy.

A Study on the Additional Absorbed Dose of Normal Tissues by Image Guided Radiation Therapy(IGRT) (영상유도 방사선 치료(IGRT)에 따른 정상 조직의 추가 피폭에 대한 연구)

  • Kim, Gha-Jung;Ryu, Jun-Min;Choi, Jun-Gu;Hong, Dong-Hee
    • The Journal of the Korea Contents Association
    • /
    • v.16 no.1
    • /
    • pp.75-81
    • /
    • 2016
  • The recent radiation therapy field can provide treatment which guarantees a high degree of accuracy, due to patient set-up using various image guided radiation therapy(IGRT) instruments. But the additional absorbed dose to patient's normal tissues is increasing. Therefore, this study measured the absorbed dose to surrounding normal tissues which is caused by patient set-up using OBI, CBCT, ExacTrac, among various IGRT instruments. The absorbed dose to the head, the chest, the abdomen, and the pelvis from CBCT was 12.57 mGy, 20.82 mGy, 82.93 mGy, and 52.70 mGy, respectively. Also, the absorbed dose from OBI and ExacTrac ranged from 0.76 to 8.58 mGy and from 0.14 to 0.63 mGy, respectively. As a result, CBCT's absorbed dose was far higher than other instruments. CBCT's surface dose was far higher than others, too, but OBI's entrance skin dose was almost the same as CBCT's.

Numerical Calculations of IASCC Test Worker Exposure using Process Simulations (공정 시뮬레이션을 이용한 조사유기응력부식균열 시험 작업자 피폭량의 전산 해석에 관한 연구)

  • Chang, Kyu-Ho;Kim, Hae-Woong;Kim, Chang-Kyu;Park, Kwang-Soo;Kwak, Dae-In
    • Journal of the Korean Society of Radiology
    • /
    • v.15 no.6
    • /
    • pp.803-811
    • /
    • 2021
  • In this study, the exposure amount of IASCC test worker was evaluated by applying the process simulation technology. Using DELMIA Version 5, a commercial process simulation code, IASCC test facility, hot cells, and workers were prepared, and IASCC test activities were implemented, and the cumulative exposure of workers passing through the dose-distributed space could be evaluated through user coding. In order to simulate behavior of workers, human manikins with a degree of freedom of 200 or more imitating the human musculoskeletal system were applied. In order to calculate the worker's exposure, the coordinates, start time, and retention period for each posture were extracted by accessing the sub-information of the human manikin task, and the cumulative exposure was calculated by multiplying the spatial dose value by the posture retention time. The spatial dose for the exposure evaluation was calculated using MCNP6 Version 1.0, and the calculated spatial dose was embedded into the process simulation domain. As a result of comparing and analyzing the results of exposure evaluation by process simulation and typical exposure evaluation, the annual exposure to daily test work in the regular entrance was predicted at similar levels, 0.388 mSv/year and 1.334 mSv/year, respectively. Exposure assessment was also performed on special tasks performed in areas with high spatial doses, and tasks with high exposure could be easily identified, and work improvement plans could be derived intuitively through human manikin posture and spatial dose visualization of the tasks.

Caregiver or Family Doses due to Discharged $^{131}I$ Administrated Patient from the Hospital (고용량 $^{131}I$ 투여환자 퇴원이후 환자 간병인과 환자 가옥의 피폭선량 측정)

  • Jeong, Gyu-Hwan;Lee, Hyun-Kook;Cho, Woon-Kap;Lee, Jai-Ki
    • Journal of radiological science and technology
    • /
    • v.33 no.2
    • /
    • pp.149-154
    • /
    • 2010
  • Exposed doses to the patient's caregiver and their house due to the 131I from patients discharged from the hospital were measured using OSL dosimeters. Usually, 3.37-5.55 GBq (100-150 mCi) of $^{131}I$ administrated patients are discharged from the hospital after 3 or 4 days of hospitalization in Korea. In addition, after 5 to 8 days, the accumulated doses of the patient's caregiver and house after hospitalization of the patient were measured using OSL dosimeters. The results of the measured average accumulated doses were 0.1 mSv, which is 10% of 1 mSv, the public dose limit in the Korean Atomic Energy Law. And it's standard deviation was 0.087 mSv. Based on the results of this study, we anticipate that we could assure the compliance of the regulation requirement 5 mSv of MEST (Ministry of Education, Science and Technology) Notice No. 2008-45 for the patient's caregiver or family, even if we reduce the 3-4 days of hospitalization to 1-2 days or less.