• Title/Summary/Keyword: 내부선량

Search Result 246, Processing Time 0.021 seconds

Indoor Radon Levels and Effective Dose Estimation in Learning and Common Living Space of University (대학 내 학습공간과 공동 생활공간에 대한 실내 라돈 농도 측정과 유효선량 산출)

  • Kim, Jung-Su
    • Journal of the Korean Society of Radiology
    • /
    • v.12 no.3
    • /
    • pp.329-334
    • /
    • 2018
  • Radon which is natural component of air is a colorless and odorless radioactive gas. Radon exposure can also occur from some building materials if they are made from radon-containing substances by breathing. In this study, The radiation dose of radon concentration was detected at 8 buildings of the A university during 3-month from June. 2017 to August. 2017. We detected indoor radon exposure at 8 building of the university and estimated annual effective dose. The radon concentration of Hall G and Hall F of the A university represented 81 and $14Bq/m^3$ respectively and average indoor radon concentration represented $41.63Bq/m^3$. Average effective dose was estimated 0.40 mSv/y, maximum effective dose was 0.78 mSv/y and minimum effective dose was 0.13 mSv/y respectively. University is the place that students spend the almost whole time. We suggest ventilation and appropriate management of a building, which could reduce the natural radiation exposure by radon concentration.

MeV급 양성자 빔을 이용한 PMMA 리소그래피

  • Choi, Han-Woo;Woo, Hyung-Joo;Hong, Wan;Kim, Young-Seok;Kim, Gi-Dong;Kim, Jun-Gon
    • Proceedings of the Korean Vacuum Society Conference
    • /
    • 2000.02a
    • /
    • pp.90-90
    • /
    • 2000
  • 이온빔을 이용한 리소그래피의 경우 미크론 이하의 미세구조를 형성할 수 있는 유용한 수단으로서 방사광 X-선과 함께 주목을 받고 있으며, 이와 같은 미세구조 제작은 MEMS (Micro Electro-Mechanical System) 개발에 있어서 매우 중요하다. 그러나 이온빔을 이용한 리소그래피에 대한 연구가 많이 이루어져 있지 않은 상태이다. MeV급 양정사 빔을 이용한 리소그래피의 가능성을 확인하기 위하여 기본적인 실험을 수행하였으며, 최적 이온빔 조사 조건 및 최적 현상 조건을 도출하였다. Resist로는 PMMA를 사용하였으며, 1.8 MeV 양성자 빔을 사용하여 50$\mu\textrm{m}$ 깊이의 구조물을 만들었다. 1.8MeV 양성자 빔의 조사선량이 7x1013ions/cm2 이상이 되면 PMMA 내부에 기포가 형성되므로 적정 조사선량을 4x1013 ions/cm2으로 결정하였다. 또한 선량을 4x1013ions/cm2 으로 고정하고 선량률을 변화시켜주면 선량률이 8x1011ions/cm2S 일 때부터 시료에 기포나 터짐 현상 등의 문제가 발생하였으며 5x1010~~1x1010ions/cm2s 의 선량률이 조사시간, 결함측면에서 가장 적합한 영역임을 알 수 있었다. 현상제로는 20% morpholine, 5% etanolamine 60% diethylenglykol-monobutylether, 15% 증류수를 혼합하여 사용하였다. 현상 온도를 30~5$0^{\circ}C$로 변화시켜서 현상을 한 결과, 4$0^{\circ}C$에서 현상 소요시간은 1시간 이내이며 SEM으로 관찰된 표면의 상태도 제일 양호한 결과를 보였다. 82 mesh 밀도, 선굵기 60$\mu\textrm{m}$, 크기 20x20 mm인 백금 망을 마스크로 사용하여 실제 3차원 미세구조를 제작하여 보았다. 그림 1에서 제작된 구조물의 SEM 사진을 보여주었으며, 식각된 면의 조도가 매우 뛰어나며 모서리의 직각성도 우수함을 확인할 수 있다. 이와 같이 도출된 시험 조건을 기초로 하여 리소그래피 후에 전기 도금을 이용한 금속 몰드 제작 및 이온빔 리소그래피 장점을 최대한 살릴수 있는 미세구조 제작에 대한 연구를 계속 추진할 계획이다.

  • PDF

A Study on the Clearance Level(draft) for the Steel Scrap from the KRR-1 & 2 Decommissioning (연구로 1,2호기 해체 철재폐기물의 규제해제농도기준(안) 도출을 위한 연구)

  • 홍상범;이봉재;정운수
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.2 no.1
    • /
    • pp.60-67
    • /
    • 2004
  • The exposure dose form recycling of a large amount of the steel scrap from the KRR-1&2 decommissioning activities was evaluated, and also the clearance level(draft) was derived. The maximum individual dose and collective dose were evaluated by modifying internal dose conversion factor which was based on the concept of effective dose in ICRP 60, applied to the RESRAD-RECYCLE ver 3.06 computing code, IAEA Safety Series 111-P-1.1 and NUREG-1640 as the assessment tool. The result of assessment for individual dose and collective dose is 23.9 $\mu$Sv per year and 0.11 man$.$Sv per year respectively. The clearance levels were ultimately determined by extracting the most conservative value form the results of the generic assessment and specific assessment methodologies. The result of clearance level for radionuclides( $Co^{60}$ , C $s^{l37}$) is less than 1.14${\times}$10$^{-1}$ Bq/g to comply with the clearance criterion(maximum individual dose : 10 $\mu$Sv per year, collective dose : 1 man$.$Sv per year) provided for Korea Atomic Energy Act and relevant regulations.s.

  • PDF

Effect of Low Magnetic Field on Dose Distribution in the Partial-Breast Irradiation (부분유방 방사선조사 시 저자기장이 선량분포에 미치는 영향)

  • Kim, Jung-in;Park, So-Yeon;Lee, Yang Hoon;Shin, Kyung Hwan;Wu, Hong-Gyun;Park, Jong Min
    • Progress in Medical Physics
    • /
    • v.26 no.4
    • /
    • pp.208-214
    • /
    • 2015
  • The aim of this study is to investigate the effect of low magnetic field on dose distribution in the partial-breast irradiation (PBI). Eleven patients with an invasive early-stage breast carcinoma were treated prospectively with PBI using 38.5 Gy delivered in 10 fractions using the $ViewRay^{(R)}$ system. For each of the treatment plans, dose distribution was calculated with magnetic field and without magnetic field, and the difference between dose and volume for each organ were evaluated. For planning target volume (PTV), the analysis included the point minimum ($D_{min}$), maximum, mean dose ($D_{mean}$) and volume receiving at least 90% ($V_{90%}$), 95% ($V_{95%}$) and 107% ($V_{107%}$) of the prescribed dose, respectively. For organs at risk (OARs), the ipsilateral lung was analyzed with $D_{mean}$ and the volume receiving 20 Gy ($V_{20\;Gy}$), and the contralateral lung was analyzed with only $D_{mean}$. The heart was analyzed with $D_{mean}$, $D_{max}$, and $V_{20\;Gy}$, and both inner and outer shells were analyzed with the point $D_{min}$, $D_{max}$ and $D_{mean}$, respectively. For PTV, the effect of low magnetic field on dose distribution showed a difference of up to 2% for volume change and 4 Gy for dose. In OARs analysis, the significant effect of the magnetic field was not observed. Despite small deviation values, the average difference of mean dose values showed significant difference (p<0.001), but there was no difference of point minimum dose values in both sehll structures. The largest deviation for the average difference of $D_{max}$ in the outer shell structure was $5.0{\pm}10.5Gy$ (p=0.148). The effect of low magnetic field of 0.35 T on dose deposition by a Co-60 beam was not significantly observed within the body for PBI IMRT plans. The dose deposition was only appreciable outside the body, where a dose build-up due to contaminated electrons generated in the treatment head and scattered electrons formed near the body surface.

Gross Alpha Analysis of Nasal Smear Samples and Internal Dose Assessment Procedure in Radiation Emergency (방사선비상시 비강스메어 시료의 전알파 분석 및 내부피폭선량평가 절차)

  • Yoon, Seokwon;Ha, Wi-Ho;Kim, Mee-Ryeong;Lee, Seung-Sook
    • 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.

Comparative Analyses of the Internal Radiation Exposures due to Food Chain Pathway Using FOOD III Code (FOOD III 코드를 이용한 섭식경로 내부피폭 비교해석)

  • Choi, Yong-Ho;Chung, Kyu-Hoi;Kim, Jin-Kyu;Lee, Jeong-Ho
    • Journal of Radiation Protection and Research
    • /
    • v.13 no.2
    • /
    • pp.41-51
    • /
    • 1988
  • In order to develop a food-chain computer code suitable to the environmental conditions of Korea, the FOOD III code was partially modified. The excution results for Korean male-adult were compared to those from the Canadian version of FOOD III to deduce a more realistic approach in dose assessment. The amounts of Mn-54, Co-58, Co-60, I-131 and I-132 released from Kori unit 1 in1984 were used as the source terms for the sample calculation. The maximum atmospheric dispersion factor(X/Q) value on the site boundary was applied. Through the code modification, organ doses decreased by about $20{\sim}70%$ and the effective committed dose equivalent by about 40% to be $7.935{\times}10^{-6}Sv/y$ which is 0.16% of the ICRP limit, $5{\times}10^{-3}Sv/y$.

  • PDF

Development of Unmanned Remote Radiation Detection Module (무인 원격 방사선 검출 모듈 개발)

  • Chang, Bo-Seok
    • Journal of the Korean Society of Radiology
    • /
    • v.15 no.6
    • /
    • pp.795-801
    • /
    • 2021
  • The designed drone-based unmanned remote radiation detection module was developed according to the needs of the nuclear power plant decommissioning workshop. Using the Geiger-Mueller tube sensitive to low-level radiation measurement, It was manufactured to measure the amount of radiation leaking into and out of the containment vessel. The drone-based radiation detection module weighs less than 200g, It can be operated inside and outside the containment vessel of a nuclear power plant. To check the performance of the designed equipment, a performance evaluation test was conducted with reference to the international standard (IEC-60864). The stability of the radiation detection module designed to meet the needs of the field the statistical rate of change by repeated measurements in the rate of change experiment to evaluate the measurement accuracy was ±4.6%. The accuracy ±7.3% in the linearity experiment to evaluate the dose rate dependence, the linear The figure satisfies the international performance evaluation standard of ±3.5%. The radiation detection module developed in this study is a customized equipment for a nuclear power plant dismantling workshop. It will be helpful for accurate measurement of space dose rate and safety management of radiation worksites in sites with a lot of radiation dust.

Study on Development of Patient Effective Dose Calculation Program of Nuclear Medicine Examination (핵의학검사의 환자 유효선량 계산 프로그램 제작에 관한 연구)

  • Seon, Jong-Ryul;Gil, Jong-Won
    • Journal of the Korea Academia-Industrial cooperation Society
    • /
    • v.18 no.3
    • /
    • pp.657-665
    • /
    • 2017
  • The aim of this study was to develop and distribute a dedicated program that can easily calculate the effective dose of a patient undergoing nuclear medicine examinations, and assist in the study of dose of nuclear medicine examinations and information disclosure. The program produced a database of the effective dose per unit activity administered (mSv/MBq) of the radiopharmaceuticals listed in ICRP 80, 106 Report and the fourth addendum, was designed through Microsoft Visual Basic (In Excel) to take the effect of 5 different (Area, Clark, Solomon(=Fried), Webster, Young) of pediatric dose calculation methods and 7 different body surface area calculation methods. The program calculates the effective dose (mSv) when the age, radionuclide, substance, and amount injected in the human body is inputted. In pediatric cases, when the age is entered, the pediatric method is activated and the pediatric method to be applied can be selected. When the BSA (Body Surface Area) formula is selected in the pediatric calculation method, a selection window for selecting the body surface area calculation method is activated. When the adult dose is input, the infant dose and the effective dose (mSv) are calculated automatically. The patient effective dose calculation program of the nuclear medicine examinations produced in this study is meaningful as a tool for calculating the internal exposure dose of the human body that is most likely to be obtained in nuclear medicine examinations, even though it is not the actual measurement dose. In the future, to increase the utilization of the program, it will be produced as an application that can be used in mobile devices, so that the public can access it easily.