• 제목/요약/키워드: Radiation Counter

검색결과 133건 처리시간 0.027초

2차원 방사선준위 분포측정 시스템의 제작 및 특성 조사 (The Characteristics of Two-dimensional Radiation Monitoring System)

  • 김성환;한상효;김계령;강희동;최영수;이용범;이종민
    • 센서학회지
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    • 제6권4호
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    • pp.290-297
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    • 1997
  • 본 연구에서는 CsI(TI) 섬광계수기를 이용하여 고방사선장에서 방사선준위분포를 측정할 수 있는 2차원 측정시스템을 개발하였다. 콜리메이터의 내경이 8 mm일 때 최적의 위치분해능과 검출효율을 얻었으며 이때 위치분해능은 1 m 거리에서 10 cm미만이었다. 그리고 시스템의 에너지 분해능은 Cs-137의 662 keV에 대하여 10 %, Co-60의 1.17 MeV에 대하여 7.6 %, 1.33 MeV에 대하여 5.8 %를 얻었다. 그리고 실제 방사선 선원에 대하여 그 분포를 측정할 수 있었다.

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Determination of counting efficiency considering the biodistribution of 131I activity in the whole-body counting measurement

  • MinSeok Park ;Jaeryong Yoo;Minho Kim ;Won Il Jang ;Sunhoo Park
    • Nuclear Engineering and Technology
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    • 제55권1호
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    • pp.295-303
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    • 2023
  • Whole-body counters are widely used to assess internal contamination after a nuclear accident. However, it is difficult to determine radioiodine activity due to limitations in conventional calibration phantoms. Inhaled or ingested radioiodine is heterogeneously distributed in the human body, necessitating time-dependent biodistribution for the assessment of the internal contamination caused by the radioiodine intake. This study aims at calculating counting efficiencies considering the biodistribution of 131I in whole-body counting measurement. Monte Carlo simulations with computational human phantoms were performed to calculate the whole-body counting efficiency for a realistic radioiodine distribution after its intake. The biodistributions of 131I for different age groups were computed based on biokinetic models and applied to age- and gender-specific computational phantoms to estimate counting efficiency. After calculating the whole-body counting efficiencies, the efficiency correction factors were derived as the ratio of the counting efficiencies obtained by considering a heterogeneous biodistribution of 131I over time to those obtained using the BOMAB phantom assuming a homogeneous distribution. Based on the correction factors, the internal contamination caused by 131I can be assessed using whole-body counters. These correction factors can minimize the influence of the biodistribution of 131I in whole-body counting measurement and improve the accuracy of internal dose assessment.

양방사선 골밀도 측정 장치의 공간산란선량분포측정 (Bone Density Spatial Distribution of Radiation Dose Measurement)

  • 김선칠;원도연;박창희;동경래
    • 대한디지털의료영상학회논문지
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    • 제13권2호
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    • pp.59-62
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    • 2011
  • In this experiment, how DEXA(Dual-energy X-ray Absorptiometry) bone mineral density was measured using the equipment. In order to maintain the same measurement conditions, bone mineral density measurements of 10 cm thick phantom, with an actual patient at a point when examining the same conditions(100 kVp, 1 mA) and then out to the five doses of radiation and its average was calculated by dividing measured. X-ray dose rate measured at the Research Institute, Sword of the gamma survey meters calibrated MEDCOM Ltd. (Inspector GM counter tube) was used, calibration factor is 1.15. On a horizontal plane around the patient, depending on the distance was significantly reduced dose rate. In addition, orientation $0^{\circ}$ head end was higher in the direction of the highest dose rate, $0^{\circ}$ $180^{\circ}$ direction from the direction towards the higher dose rate reduced to some extent in the direction of all the $120^{\circ}$ were able to identify.

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$^{188}He$을 이용한 혈관내 방사선 치료시 시술자의 방사선 피폭 수준 (Radiation Exposure of Operator in Intracoronary Radiotherapy Using $^{188}Re$)

  • 지의규;이명묵;우홍균
    • Journal of Radiation Protection and Research
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    • 제25권4호
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    • pp.191-195
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    • 2000
  • 현재 서울대학교병원에서 진행중인 연구의 일환으로 혈관 내 방사선치료 시 시술자의 방사선피폭 정도 및 위험성에 대해 알아보고자 연구를 시행하였다. 심장혈관 폐색으로 연구에 포함되어 방사선치료른 시행 받은 42명의 환자 중 측정이 완벽한 34명의 자료를 토대로 분석을 시행하였다. 혈관내 방사선치료는 관상동맥성형술 직후 풍선도자법을 이용하여 대상 동맥의 중막에 17 Gy를 조사하였다. 사용된 동위원소는 $^{188}Re$이었으며 GM측정기로 각기 다른 8점에서 피폭선량을 측정하였다. 환자의 심장부위에서 10cm, 40cm 떨어진 지점을 시술자의 최대피폭량, 전신피폭량의 기준으로 삼았다. 치료선량의 중앙값은 111.6 mCi이었고 중앙치료시간은 576초였다. 환자 심장부위에서 l0cm, 40cm 지점의 평균 피폭 선량율은 0.43 mSv/hr, 0.30 mSv/hr 이었고, 각 지점에서의 시술 당 평균 피폭 선량은 0.07 mSv, 0.05 mSv 이었다. 이 수치는 ICRP-60나 과학기술부 고시에서 권고하고 있는 한계 피폭선량보다 훨씬 적은 값으로 현재 저울대학교병원에서 시행하고 있는 혈관내 방사선 치료법은 방사선방어 면에서 매우 안전한 방법임을 확인할 수 있었다.

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일사량 에너지 데이터 관리 시스템 설계 (Design of Solar Radiation Energy Data Management System)

  • 오인배;안윤애;류근호;김광득
    • 정보처리학회논문지D
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    • 제10D권3호
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    • pp.531-540
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    • 2003
  • 에너지 사용의 급증으로 인해 환경오염, 지구 온난화 현상, 오일 파동의 문제가 발생되고 있다. 이를 해결하기 위해 태양 에너지, 풍력, 소수력 등과 같은 대체에너지에 대한 관심이 매우 높아지고 있다. 미국, 유럽, 일본에서는 대체에너지원의 정보를 체계적으로 관리하고 활용하기 위한 시스템 개발에 많은 노력을 하고 있다. 그러나 국내에서는 아직 대체에너지 정보 시스템이 효과적으로 구축되지 못하고 있다. 따라서 이 논문에서는 일사량 에너지 데이터를 저장 및 관리하는 대체에너지 정보 시스템을 제안한다. 이 시스템은 ArcView GIS를 이용하여 구현되었으며, 다양한 시공간 질의를 사용한 데이터 검색이 가능하도록 하였다. 아울러 사용자는 질의 결과를 챠트, 그래프, 등고선과 같은 형태로 확인할 수 있다. 구현된 시스템은 ArcIMS를 이용하여 인터넷 웹 서비스를 제공한다.

첼렌코프광과 액체섬광계수법을 이용한 89Sr 및 90Sr 분석에 대한 연구 (A Study on the Analysis of 89Sr and 90Sr with Cerenkov Radiation and Liquid Scintillation Counting Method)

  • 이명호;조영현;정근호;최근식;이창우
    • 분석과학
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    • 제15권1호
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    • pp.20-25
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    • 2002
  • 추출크로마토그래피와 액체섬광계수기를 이용하여 기존의 방사성 스트론튬 분석법 단점을 해결하는 신속하고 신뢰성 있는 $^{89}Sr$$^{90}Sr$ 분석법을 개발하였다. 옥살산 공침혹은 양이온 교환수지로 방해원소를 제거한 후 Sr-spec 컬럼을 사용하여 스트론튬만을 순수분리한 후, 액체섬광계수기를 사용하여 $^{89}Sr$에서 방출하는 첼렌코프광을 측정하였고 spectrum unfolding 방법으로 $^{90}Sr$을 정량하였다. 본 연구에서 개발된 방사성 스트론튬 분석법을 환경 표준시료 (IAEA-375, Soil) 및 액체 폐기물시료에 적용하여 분석법의 유효성을 검증하였다.

산화제 제어 확산화염의 화염구조 및 NO 생성 특성에 관한 수치해석적 연구 (Numerical Study on Flame Structure and NO Formation Characteristics in Oxidizer-Controlled Diffusion Flames)

  • 이창언;한지웅
    • 대한기계학회논문집B
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    • 제26권5호
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    • pp.742-749
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    • 2002
  • Numerical Study with detailed chemistry has been conducted to investigate the flame structure and NOx formation characteristics in oxygen -enhanced(CH$_4$/O$_2$-$N_2$) and oxygen-enhanced-EGR(CH$_4$/O$_2$-$CO_2$) counter diffusion flame with various strain rates. A small amount of $N_2$is included in oxygen-enhanced-EGR combustion, in order to consider the inevitable $N_2$contamination by $O_2$production process or air infiltration. The results are as follows : In CH$_4$/O$_2$-$CO_2$flame it is very important to adopt a radiation effect precisely because the effect of radiation changes flame structure significantly. In CH$_4$/O$_2$-$N_2$flame special strategy to minimize NO emission is needed because it is very sensitive to a small amount of $N_2$. Special attention is needed on CO emission by flame quenching, because of increased CO concentration. Spatial NO production rate of oxygen-enhanced combustion is different from that of air and oxygen-enhanced-EGR combustion in that thermal mechanism plays a role of destruction as well as production. In case CH$_4$/O$_2$-$CO_2$flame contains more than 40% $CO_2$it is possible to maintain the same EINO as that of CH$_4$/Air flame with accomplishing higher temperature than that of CH$_4$/Air flame. EINO decreases with increasing strain rate, and those effects are augmented in CH$_4$/O$_2$flame.

산화제 제어 화염의 구조 및 NO 생성 특성 (Structure and NO formation characteristics of oxidizer-controlled diffusion flames)

  • 한지웅;이창언
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 추계학술대회논문집B
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    • pp.185-190
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    • 2001
  • Numerical Study with detailed chemistry has been conducted to investigate the flame structure and NOx formation characteristics in oxygen-enhanced$(CH_4/O_2-N_2)$ and oxygen-enhanced-EGR$(CH_4/O_2-CO_2)$ counter diffusion flame with various strain rates. A small amount of $N_2$ is included in oxygen-enhanced-EGR combustion, in order to consider the inevitable $N_2$ contamination by $O_2$ production process or air infiltration. The results are as follows : In $CH_4/O_2-CO_2$ flame it is very important to adopt a radiation effect precisely because the effect of radiation changes flame structure significantly. In $CH_4/O_2-N_2$ flame special strategy to minimize NO emission is needed because it is very sensitive to a small amount of $N_2$. Special attention is needed on CO emission by flame quenching, because of increased CO concentration. Spatial NO production rate of oxygen-enhanced combustion is different from that of air and oxygen-enhanced-EGR combustion in that thermal mechanism plays a role of destruction as well as production. In case $CH_4/O_2-CO_2$ flame contains more than 40% $CO_2$ it is possible to maintain the same EINO as that of $CH_4/Air$ flame with accomplishing higher temperature than that of $CH_4/Air$ flame. EINO decreases with increasing strain rate, and those effects are augmented in $CH_4/O_2$ flame. Complementary study is needed with extending the range of strain rate variation.

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Preparation of 125

  • Kim, Byoung-Soo;Kim, Eun-Jung;Lee, Hae-June;Han, Sang-Jin;Choi, Tae-Hyun;Lee, Yun-Sil;Cheon, Gi-Jeong
    • Bulletin of the Korean Chemical Society
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    • 제31권9호
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    • pp.2649-2655
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    • 2010
  • $PKC{\delta}$-catalytic V5 Heptapeptide (FEQFLDI, FP7) interacts with heat shock protein 27 (HSP27) and inhibits HSP27-mediated resistance to cell death against various stimuli including radiation therapy. Here, we prepared radio-iodinated heptapeptide and further investigated its uptake properties in HSP27 expression cells. Peptide sequence of FP7 and a negative control peptide (WSLLEKR, QP7) was modified by substituting their C-terminus residue to tyrosine (FP6Y and QP6Y) to label radio-iodine. Iodinated peptides were confirmed by LC mass analysis with cold iodine reaction mixture. Accumulation of [$^{125}I$]iodo-FP6Y and [$^{125}I$]iodo-QP6Y in NCI-H1299 cell line, with higher level of HSP27, and NCI-H460 cell line, with lower level of HSP27, was measured by NaI(Tl) scintillation counter. The modification of substituting C-terminus residue of FP7 to tyrosine (FP6Y) did not affect its interaction with HSP27. Accumulation of [$^{125}I$]iodo-FP6Y in NCI-H1299 cells was 3 fold higher than in NCI-H460 cells. The novel radio-iodinated FP6Y would be used as a tracer for targeting HSP27 protein.

An Intercomparison of Counting Efficiency and the Performance of Two Whole-Body Counters According to the Type of Phantom

  • Pak, Minjung;Yoo, Jaeryong;Ha, Wi-Ho;Jin, Young-Woo
    • Journal of Radiation Protection and Research
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    • 제41권3호
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    • pp.274-281
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    • 2016
  • Background: Whole-body counters are widely used to evaluate internal contamination of the internal presence of gamma-emitting radionuclides. In internal dosimetry, it is a basic requirement that quality control procedures be applied to verify the reliability of the measured results. The implementation of intercomparison programs plays an important role in quality control, and the accuracy of the calibration and the reliability of the results should be verified through intercomparison. In this study, we evaluated the reliability of 2 whole-body counting systems using 2 calibration methods. Materials and Methods: In this study, 2 whole-body counters were calibrated using a reference male bottle manikin absorption (BOMAB) phantom and a Radiation Management Corporation (RMC-II) phantom. The reliability of the whole-body counting systems was evaluated by performing an intercomparison with International Atomic Energy Agencyto assess counting efficiency according to the type of the phantom. Results and Discussion: In the analysis of counting efficiency using the BOMAB phantom, the performance criteria of the counters were satisfied. The relative bias of activity for all radionuclides was -0.16 to 0.01 in the Fastscan and -0.01 to 0.03 in the Accuscan. However, when counting efficiency was analyzed using the RMC- II phantom, the relative bias of $^{241}Am$ activity was -0.49 in the Fastscan and 0.55 in the Accuscan, indicating that its performance criteria was not satisfactory. Conclusion: The intercomparison process demonstrated the reliability of whole-body counting systems calibrated with a BOMAB phantom. However, when the RMC-II phantom was used, the accuracy of measurements decreased for low-energy nuclides. Therefore, it appears that the RMC-II phantom should only be used for efficiency calibration for high-energy nuclides. Moreover, a novel phantom capable of matching the efficiency of the BOMAB phantom in low-energy nuclides should be developed.