• 제목/요약/키워드: Absorbed dosimetry

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악관절 단층촬영시의 두경부 주요 기관의 흡수선량 (Absorbed Doses in Organs of the Head and Neck from Conventional Temporomandibular Joint Tomography)

  • 조봉혜
    • 치과방사선
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    • 제29권2호
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    • pp.411-416
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    • 1999
  • Purpose : This study was done to evaluate the absorbed doses in organs of the head and neck for the conventional temporomandibular joint tomography. Materials and Methods : Dosimetry was performed with 32 LiF thermoluminescent dosimeters, which were placed in a tissue-equivalent phantom when the temporomandibular joint was examined by both lateral and frontal temporomandibular joint tomography. Results : For lateral tomography, parotid gland and preauricular area towards tube showed relatively high absorbed dose of 1056.9 μGy and 519.9 μGy respectively. For frontal tomography, the two largest absorbed doses were 259.2 μGy in orbit towards tube and 212.0 μGy in lens towards tube. Conclusion : Conventional temporomandibular joint tomography showed relatively low absorbed doses on critical organs. Thus, responsible use of it may not be limited.

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고 에너지 광자선의 표준측정법에 대한 선량 교정 프로그램 개발 (Development of a Dose Calibration Program for Various Dosimetry Protocols in High Energy Photon Beams)

  • 신동오;박성용;지영훈;이창건;서태석;권수일;안희경;강진오;홍성언
    • Radiation Oncology Journal
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    • 제20권4호
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    • pp.381-390
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    • 2002
  • 목적 : 고 에너지 광자선에 대한 기준점에서의 물 흡수선량 계산을 절차상 또는 계산상의 오류를 피하기 위해 공기커마(혹은 조사선량) 교정정수에 토대를 두고 있는 IAEA TRS-277과 AAPM TG-21 및 최근 발표된 새로운 개념의 물 흡수선량 교정정수에 토대를 두고 있는 IAEA TRS-398과 AAPM TG-51 표준측정법에 기초한 고 에너지 광자선의 선량 교정 프로그램을 개발하고자 한다. 대상 및 방법 : 현재 국내외에서 널리 사용되고 있는 고 에너지 광자선에 대한 흡수선량 표준측정법은 IAEA TRS-277과 AAPM TG-21로서 공기커마(혹은 조사선량) 교정정수에 토대를 두고 있어 수식 체계가 복잡하고, 사용된 물리량에 대한 불확정도가 커서 선량측정의 정확성을 향상시키는데 한계가 있다. 최근 국제원자력기구와 미국의학물리학회에서는 새로운 개념의 물 흡수선량 교정정수에 토대를 두고 있는 IAEA TRS-398과 AAPM TG-51을 발표하였다. 개발된 네 종류의 선량 교정 프로그램은 이들 표준측정법에서 사용되고 있는 수식체계와 물리적인 매개변수를 엄격하게 적용하였고, 선량계에 대한 정보 및 물리적인 값에 대한 표와 그래프 값은 수치화하여 데이터베이스화하였다. 이들 프로그램은 윈도우 환경에서 사용이 용이하도록 비쥬얼 $C^{++}$ 언어를 사용하여 각각의 표준측정법에서 권고하고 있는 방법 및 절차에 따라 사용자의 편의성을 고려하여 개발하였다. 결과 : 네 종류의 표준측정법에 대하여 개발된 고 에너지 광자선에 대한 선량 교정 프로그램은 사용자가 병원에서 사용하고 있는 표준측정법을 선택하여 선량측정 절차에 따라 선량계, 선질 특성 및 측정 조건에 관한 정보와 측정 결과를 입력하고, 순차적으로 수행하도록 되어 있어 절차상 혹은 선량 계산에 있어서 사용자간의 오차 및 실수를 최소화할 수 있었다 또한 서로 다른 개념의 네 종류의 표준측정법에 대한 기준점에서의 선량값을 상호 비교할 수 있었다. 결론 : 이 프로그램은 이온함에 대한 정보와 물리적인 자료에 대한 표와 그래프 값들을 수식화하여 데이터베이스함으로써 수작업으로 각 프로토콜의 수행 절차상 혹은 사용자간의 발생할 수 있는 개인적인 실수 및 오차를 줄일 수 있었다. 또한 이 프로그램은 사용자 편의성을 고려하였고, 모든 보정계수와 물흡수선량을 정확하게 계산할 수 있기 때문에 각 표준측정법에 대한 주요한 차이점을 비교 분석할 수 있어 사용자가 적당한 표준측정법을 선택하여 수행하므로써 고 에너지 광자선 선량 교정에 이용시 매우 유익할 것으로 사료된다.

A Convenient System for Film Dosimetry Using NIH-image Software

  • Kurooka, Masahiko;Koyama, Syuji;Obata, Yasunori;Homma, Mitsuhiko;Imai, Kuniharu;Tabushi, Katsuyoshi
    • 한국의학물리학회:학술대회논문집
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    • 한국의학물리학회 2002년도 Proceedings
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    • pp.260-262
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    • 2002
  • An accurate measurement of dose distribution is indispensable to perform radiation therapy planning. A measurement technique using a radiographic film, which is called a film dosimetry, is widely used because it is easy to obtain a dose distribution with a good special resolution. In this study, we tried to develop an analyzing system for the film dosimetry using usual office automation equipments such as a personal computer and an image scanner. A film was sandwiched between two solid water phantom blocks (30 ${\times}$ 30 ${\times}$ 15cm). The film was exposed with Cobalt-60 ${\gamma}$-ray whose beam axis was parallel to the film surface. The density distribution on the exposed film was stored in a personal computer through an image scanner (8bits) and the film density was shown as the digital value with NIH-image software. Isodose curves were obtained from the relationship between the digital value and the absorbed dose calculated from percentage depth dose and absorbed dose at the reference point. The isodose curves were also obtained using an Isodose plotter, for reference. The measurements were carried out for 31cGy (exposure time: 120seconds) and 80cGy (exposure time: 300seconds) at the reference point. While the isodose curves obtained with our system were drawn up to 60% dose range for the case of 80cGy, the isodose curves could be drawn up to 80% dose range for the case of 31cGy. Furthermore, the isodose curves almost agreed with that obtained with the isodose plotter in low dose range. However, further improvement of our system is necessary in high dose range.

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Thermally assisted IRSL and VSL measurements of display glass from mobile phones for retrospective dosimetry

  • Discher, Michael;Kim, Hyoungtaek;Lee, Jungil
    • Nuclear Engineering and Technology
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    • 제54권2호
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    • pp.429-436
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    • 2022
  • Investigations of retrospective dosimetry have shown that components of mobile phones are suitable as emergency dosimeters in case of radiological incidents. For physical dosimetry, components can be read out using optically stimulated luminescence (OSL), thermoluminescence (TL) and phototransferred thermoluminescence (PTTL) methods to determine the absorbed dose. This paper deals with a feasibility study of display glass from modern mobile phones that are measured by thermally assisted (Ta) optically stimulated luminescence. Violet (VSL, 405 nm) and infrared (IRSL, 850 nm) LEDs were used for optical stimulation and two protocols (Ta-VSL and Ta-IRSL) were tested. The aim was to systematically investigate the luminescence properties, compare the results to blue stimulated Ta-BSL protocol (458 nm) and to develop a robust measurement protocol for the usage as an emergency dosimeter after an incident with ionizing radiation. First, the native signals were measured to calculate the zero dose signal. Next, the reproducibility and dose response of the luminescence signals were analyzed. Finally, the signal stability was tested after the storage of irradiated samples at room temperature. In general, the developed Ta-IRSL and Ta-VSL protocols indicate usability, however, further research is needed to test the potential of a new protocol for physical retrospective dosimetry.

동위원소 치료 관련 방사선 흡수선량평가 (Radiation Dosimetry for Radionuclide Therapy)

  • 김은희
    • 대한핵의학회:학술대회논문집
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    • 대한핵의학회 2001년도 제40차 춘계학술대회 및 연수교육
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    • pp.4-10
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    • 2001
  • The radionuclide therapy is a protocol for tumor control by administering radionuclides as the cytotoxic agents. Radionuclides concentrated at the site of cancerous lesion are expected to kill the cancerous cells with minimal injury to the normal tissue. The efficacy of every radionuclide treatment can be evaluated by examining the toxicity to the lesion differentiated from that to the normal tissue. Radiation dosimetry is the procedure of quantitating the energy absorbed by target volumes of interest. Dosimetric information plays an indicator of the expected radiation damage and thus the therapeutic efficacy. This paper summarizes the dosimetric aspects in radionuclide therapy in terms of radionuclides of use, radiation dosimetry methodology and considerations for each treatment in practical use.

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방사선 전신 조사 : 기본 자료 측정 및 생체내에서 선량 측정 (Total Body Irradiation Technique : Basic Data Measurements and In Vivo Dosimetry)

  • 최동락;최일봉;강기문;신경섭;김춘추
    • Radiation Oncology Journal
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    • 제12권2호
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    • pp.219-223
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    • 1994
  • This paper describes the basic data measurements for total body irradiation with 6 Mv photon beam including compensators design. The technique uses bilateral opposing fields with tissue compensators for the head, neck, lungs, and legs from the hip to toes. In vivo dosimetry was carried out for determining absorbed dose at various regions in 7 patients using diode detectors(MULTIDOSE,k Model 9310, MULTIDATA Co., USA). As a results, the dose uniformity of${\pm}3.5{\%}$(generally, within${\pm}10{\%}$can be achieved with out total body irradiation technique.

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Korean-specific iodine S values for use in internal dosimetry

  • Tae-Eun Kwon;Yoonsun Chung;Choonsik Lee
    • Nuclear Engineering and Technology
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    • 제55권12호
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    • pp.4659-4663
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    • 2023
  • The use of iodine S values derived using the International Commission Radiological Protection (ICRP) phantoms may introduce significant bias in internal dosimetry for Koreans due to anatomical variability. In the current study, we produced an extensive dataset of Korean S values for selected five iodine radioisotopes (I-125, I-129, I131, I-133, and I-134) for use in radiation protection. To calculate S values, we implemented Monte Carlo simulations using the Mesh-type Reference Korean Phantoms (MRKPs), developed in a high-quality/fidelity mesh format. Noticeable differences were observed in S value comparisons between the Korean and ICRP reference phantoms with ratios (Korean/ICRP) widely ranging from 0.16 to 6.2. The majority of S value ratios were lower than the unity in Korean phantoms (interquartile range = 0.47-1.28; mean = 0.96; median = 0.69). The S values provided in the current study will be extensively utilized in iodine internal dosimetry for Koreans.

LiF(Mg, Cu, Na, Si) 열형광선량계를 사용한 $^{60}Co\;{\gamma}^-$선의 수중 흡수선량 측정 (LiF(Mg, Cu, Na, Si) Thermoluminescent Dosimeters for In-phantom Dosimetry of $^{60}Co\;{\gamma}$-rays)

  • 김현자;정운혁;이우교;도시홍
    • Journal of Radiation Protection and Research
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    • 제15권2호
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    • pp.57-65
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    • 1990
  • 새로 개발한 LiF(Mg, Cu, Na, Si) 열형광선량계를 사용하여 $^{60}Co$ 원격조사장치에 의한 수중흡수선량을 측정하였다. 공기중 조사선량으로 부터 TLD 공동의 흡수선량 교정인자($D_{TLD}$/TL)를 결정하였고, 수중흡수선량은 TLD 공동의 흡수선량을 측정하여 공동이론에 의해 해석하였다. $10{\times}10cm^2$$5{\times}10cm^2$의 빔 크기에서 팬텀내 여러지점에 대하여 LiF(Mg, Cu, Na, Si) TLD로 수중흡수선량을 결정하고 동일한 위치에서 NE 2561 전리함을 사용하여 측정한 값과 비교한 결과, LiF(Mg, Cu, Na, Si) TLD의 측정오차$({\pm}3%)$ 범위내에서 잘 일치 하였다. 빔의 크기가 $5{\times}5cm^2$, $10{\times}10cm^2$$30{\times}30cm^2$인 경우에 깊이-선량 백분율과 팬텀-공기 선량비를 측정하였으며 이 값들은 British Journal of Radiology(1983)의 데이터와 잘 일치하였다.

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X-band EPR dosimetry using minimum mass of tooth enamel for use in radiological accidents

  • Jae Seok Kim;Byeong Ryong Park;Han Sung Kim;In Mo Eo;Jaeryong Yoo;Won Il Jang;Minsu Cho;HyoJin Kim;Yong Kyun Kim
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.123-131
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    • 2024
  • Electron paramagnetic resonance (EPR) dosimetry for a tooth from an individual exposed is well known as retrospective dosimetry in radiological accidents. A major constraint of the conventional X-band tooth-EPR dosimetry is the necessity to extract the tooth of the exposed patient for dose assessment. In this study, to conduct the dose assessments of exposed patients through part-extraction of tooth enamel, the minimum detectable dose (MDD) of the tooth enamel was evaluated based on the amount of mass. Further, a field test was conducted via intercomparison using various dose assessment methods to verify the feasibility of X-band tooth-EPR dosimetry using the minimum mass of tooth enamel. The intercomparison results demonstrated that effective dose determination via X-band tooth-EPR dosimetry is reliable. Consequently, it was determined that the minimum mass of tooth enamel required to evaluate an absorbed dose above 0.5 Gy is 15 mg. Thus, EPR dosimetry using 15 mg of tooth enamel can be applied in the triage and initial medical response stages for patients exposed during radiological accidents. This approach represents an advancement in managing radiological accidents by offering a more efficient and less invasive method of dose assessment.