• Title/Summary/Keyword: PET/CT room

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Solution to Decrease Spatial Dose Rate in Laboratory of Nuclear Medicine through System Improvement (시스템 개선을 통한 핵의학 검사실의 공간 선량률 감소방안)

  • Moon, Jae-Seung;Shin, Min-Yong;Ahn, Seong-Cheol;Yoo, Mun-Gon;Kim, Su-Geun
    • Quality Improvement in Health Care
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    • v.20 no.1
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    • pp.60-73
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    • 2014
  • Objectives: This study aims at decreasing spatial dose rate through work improvement whilst spatial dose rate is the cause of increasing personal exposure dose which occurs in the process of handling radioisotope. Methods: From February 2013 until July 2013, divided into "before" and "after" the improvement, spatial dose rate in laboratory of nuclear medicine was measured in gamma image room, PET/CT-1 image room, and PET/CT-2 image room as its locations. The measurement time was 08:00, 12:00 and 17:00, and SPSS 21.0 USA was opted for its statistical analysis. Result: The spatial dose rate at distribution worktable, injection table, the entrance to the distribution room, and radioisotope storage box, which had showed high spatial dose rate, decreased by more than 43.7% a monthly average. The distribution worktable, that had showed the highest spatial dose rate in PET/CT-1 image room, dropped the rate to 42.3% as of July. The injection table and distribution worktable in the PET/CT-2 image room also showed the decline of spatial dose rate to 89% and 64.4%, respectively. Conclusion: By improving distribution process and introducing proper radiation shielding material, we were able to drop the spatial dose rate substantially at distribution worktable, injection table, and nuclide storage box. However, taking into account of steadily increasing amount of radioisotope used, strengthening radiation related regulations, and safe utilization of radioisotope, the process of system improvement needs to be maintained through continuous monitoring.

A Consideration of Apron's Shielding in Nuclear Medicine Working Environment (PET검사 작업환경에 있어서 APRON의 방어에 대한 고찰)

  • Lee, Seong-wook;Kim, Seung-hyun;Ji, Bong-geun;Lee, Dong-wook;Kim, Jeong-soo;Kim, Gyeong-mok;Jang, Young-do;Bang, Chan-seok;Baek, Jong-hoon;Lee, In-soo
    • The Korean Journal of Nuclear Medicine Technology
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    • v.18 no.1
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    • pp.110-114
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    • 2014
  • Purpose: The advancement in PET/CT test devices has decreased the test time and popularized the test, and PET/CT tests have continuously increased. However, this increases the exposure dose of radiation workers, too. This study aims to measure the radiation shielding rate of $^{18}F-FDG$ with a strong energy and the shielding effect when worker wore an apron during the PET/CT test. Also, this study compared the shielding rate with $^{99m}TC$ to minimize the exposure dose of radiation workers. Materials and Methods: This study targeted 10 patients who visited in this hospital for the PET/CT test for 8 days from May 2nd to 10th 2013, and the $^{18}F-FDG$ distribution room, patient relaxing room (stand by room after $^{18}F-FDG$ injection) and PET/CT test room were chosen as measuring spots. Then, the changes in the dose rate were measured before and after the application of the APRON. For an accurate measurement, the distance from patients or sources was fixed at 1M. Also, the same method applied to $^{99m}TC's$ Source in order to compare the reduction in the dose by the Apron. Results: 1) When there was only L-block in the $^{18}F-FDG$ distribution room, the average dose rate was $0.32{\mu}Sv$, and in the case of L-blockK+ apron, it was $0.23{\mu}Sv$. The differences in the dose and dose rate between the two cases were respectively, $0.09{\mu}Sv$ and 26%. 2) When there was no apron in the relaxing room, the average dose rate was $33.1{\mu}Sv$, and when there was an apron, it was $22.3{\mu}Sv$. The differences in the dose and dose rate between them were respectively, $10.8{\mu}Sv$ and 33%. 3) When there was no APRON in the PET/CT room, the average dose rate was $6.9{\mu}Sv$, and there was an APRON, it was $5.5{\mu}Sv$. The differences in the dose and dose rate between them were respectively, $1.4{\mu}Sv$ and 25%. 4) When there was no apron, the average dose rate of $^{99m}TC$ was $23.7{\mu}Sv$, and when there was an apron, it was $5.5{\mu}Sv$. The differences in the dose and dose rate between them were respectively, $18.2{\mu}Sv$ and 77%. Conclusion: According to the result of the experiment, $^{99m}TC$ injected into patients showed an average shielding rate of 77%, and $^{18F}FDG$ showed a relatively low shielding rate of 27%. When comparing the sources only, $^{18F}FDG$ showed a shielding rate of 17%, and $^{99m}TC$'s was 77%. Though it had a lower shielding effect than $^{99m}TC$, $^{18}F-FDG$ also had a shielding effect on the apron. Therefore, it is considered that wearing an apron appropriate for high energy like $^{18}F-FDG$ would minimize the exposure dose of radiation workers.

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Analysis of the Bacteria in Nuclear Medicine (핵의학 검사실내 세균 분석)

  • Shin, Seong-Gyu;Lee, Hyo-Yeong
    • Journal of the Korea Safety Management & Science
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    • v.19 no.2
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    • pp.95-100
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    • 2017
  • In this study, the bacterial contamination level of equipments and devices in the nuclear medicine department of a university hospital was investigated. CNS was detected from the sample collected from the door opening button of the nuclear medicine department. Bacillus sp. was detected from the table and CNS with Bacillus sp. were detected from the control button at the PET-CT room no.1. Also, CNS was detected from the table and the control button at the PET-CT room no.2. In the distribution room no.1, CNS and Bacillus sp. were detected while CNS being detected from the distribution room no.2 and CNS with Bacillus sp. being detected from the distribution room no.3. In the injection room, Enterrococcus faecium and Pontoea sp. were detected. On the table of the ecsomatics room, Pontoea sp. was detected. Bacillus sp. was detected from the inside of the syringe Pb shield and CNS was detected from the outside. Enterrococcus faecium was detected from the Gamma camera table and Bacillus sp. was detected from the door grip. On the chair at the patient waiting room, Pseudomonas aeruginosa abd Bacillus sp. were detected. Therefore, it was understood that infection should be prevented by securely sterilizing examination devices after each examination, maintaining cleanliness by regular sterilization of waiting chairs and such objects with a number of direct contacts with patients, and infection education for the features of nuclear department.

Evaluation of Temperature and Humidity of a Thermo-Hygrostat of PET/CT Equipment using a Temperature and Humidity Sensor(BME 280) (온·습도센서(BME 280 센서)를 이용한 PET/CT 장비의 항온 항습기 온·습도 평가)

  • Ryu, Chan-Ju;Kim, Jeong-A;Kim, Jun-Su;Yun, Geun-Yeong;Heo, Seung-Hui;Hong, Seong-Jong
    • Journal of the Korean Society of Radiology
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    • v.14 no.1
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    • pp.15-22
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    • 2020
  • PET(Positron Emission Tomography) devices are used as PET/CT or PET/MRI devices fused with the devices of CT or MRI for obtaining anatomical information. Therefore, the devices are constructed in circular ring-type structure whose length of gantry(the main part of filming) becomes wider and the interior depth becomes longer in comparison to other common medical equipments. scintillator, one of the components in PET devices, is inside the gantry, and as it is consisted of crystal which is sensitive to the change of temperature and humidity, large temperature change can cause the scintillator to be damaged. Though scintillator located inside the gantry maintains temperature and humidity with a thermo-hygrostat, changes in temperature and humidity are expected due to structural reasons. The output value was measured by dividing the inside of the gantry of the PET/CT device into six zones, each of which an Adafruit BME 280 temperature and humidity sensor was placed at. A thermo-hygrostat keeps the temperature and humidity constant in the PET/CT room. As the measured value of temperature and humidity of the sensor was obtained, the measured value of temperature and humidity appeared in the thermohygrostat was taken at the same time. Comparing the average measured values of temperature and humidity measured at each six zones with the average values of the thermo-hygrostat results in a difference of 2.71℃ in temperature and 21.5% in humidity. The measured temperature and humidity of PET Gantry is out of domestic quality control range. According to the results of the study, if there is continuous change in temperature and humidity in the future, the aging of the scintillator mounted in the PET Gantry is expected to be aging, so it is necessary to find a way to properly maintain the temperature and humidity inside the Gantry structure.

Comparison of the Equivalent Dose of the Lens Part and the Effective Dose of the Chest in the PET/CT Radiation Workers in the Nuclear Medicine Department (핵의학과 PET/CT실 방사선작업종사자의 수정체 부위의 등가선량과 흉부의 유효선량의 측정 비교)

  • Son, Sang-Joon;Park, Jeong-Kyu;Jung, Dong-Kyung;Park, Myeong-Hwan
    • Journal of radiological science and technology
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    • v.42 no.3
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    • pp.209-215
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    • 2019
  • Comparison of the effective dose of the chest and the equivalent dose of the lens site in the radiation workers working at four medical institutions with the PET / CT room located in one metropolitan city and province from April 1 to June 30, 2018 Respectively. Radioactive medicine were measured at the time of dispensing and at the time of injection. In this experiment, the average dispensing time per patient was 5.7 minutes and the average injection time was 3.1 minutes. The equivalent dose at the lens site was $0.78{\mu}Sv/h$ for 1 mCi, and the effective dose for chest was $0.18{\mu}Sv/h$ per 1 mCi. The equivalent dose at the lens site during injection was $0.88{\mu}Sv/h$ per mCi and the effective dose of chest was $0.20{\mu}Sv/h$ per mCi. The daily effective dose of the chest was $0.9{\pm}0.6{\mu}Sv$ and the equivalent dose of the lens site was $3.6{\pm}1.4{\mu}Sv$ during daily dosing for 20 days. The effective dose of the chest during the day was $0.6{\pm}0.5{\mu}Sv$ and the equivalent dose of the lens was $2.2{\pm}1.0{\mu}Sv$. At the time of dispensing, the equivalent dose of the lens was $0.187{\pm}0.035mSv$, the effective dose of the chest was $0.137{\pm}0.055mSv$, the equivalent dose of the lens was $0.247{\pm}0.057mSv$, and the effective dose of the monthly chest was $0.187{\pm}0.021mSv$. As a result of the corresponding sample test, the equivalent dose and the effective dose of the chest, the effective dose of the chest, the effective dose of the chest, the effective dose of the chest, The equivalent dose of the lens and the effective dose of the chest were statistically significant (p<0.05) with a significance of 0.000. However, there was no statistically significant difference (p>0.05) between the equivalent dose and the effective dose of the chest, the equivalent dose of the lens at the time of injection, and the effective dose of the chest at 0.138 and 0.230, respectively.

Correlation of SUV According to the Body Weight and Body Surface Area in PET/CT Imaging (PET/CT 검사 시 체중과 체표면적에 따른 SUV의 상관관계)

  • Park, Ju-Seon;Do, Yong-Ho;Kim, Jung-Soo;Lee, Hong-Jae;Kim, Jin-Eui
    • The Korean Journal of Nuclear Medicine Technology
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    • v.17 no.2
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    • pp.44-47
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    • 2013
  • Purpose: There are several methods of measuring SUV in PET/CT imaging including $SUV_{bw}$ which uses the body weight, $SUV_{bsa}$ which that uses body surface area and $SUV_{lbm}$ which uses lean body mass. Currently, Seoul National University Hospital uses $SUV_{bw}$ method which minimizes the variability. In this study, we compared and analyzed the correlation between $SUV_{bw}$ and $SUV_{bsa}$ according to patients' body mass index. Materials and Methods: Using Biograph mCT40 (Siemens, Germany), we conducted $^{18}F-FDG$ PET/CT imaging on 70 patients (41 males, 29 females; ages $58.04{\pm}12.44$). We classified the patients as underweight (BMI<20), normal weight (20$${\leq_-}$$BMI<25), overweight (25$${\leq_-}$$BMI<30), obese (30$${\leq_-}$$BMI<35) and severely obese (35$${\leq_-}$$BMI) according to the patient's sex, age and BIM. Then, bone, liver and lungs were set as ROI for calculation of maximum values of $SUV_{bw}$ and $SUV_{bsa}$, through Syngo.via VA11A analysis program. Results: Comparing the five groups divided according to the BMI by the standard differences between $SUV_{bw}$ to $SUV_{bsa}$, $SUV_{max}$ was measured to be $0.66{\pm}0.15$, $0.78{\pm}0.35$, $0.77{\pm}0.21$, $1.00{\pm}0.44$, $1.53{\pm}0.38$ for bones in underweight, normal weight, overweight, obese and severely obese groups, respectively. For liver, values of $SUV_{max}$ were $1.64{\pm}0.16$, $2.06{\pm}0.34$, $2.19{\pm}0.21$, $2.52{\pm}0.21$ and $2.74{\pm}0.40$ in the same order. And for lung, values of $SUV_{max}$ were $0.69{\pm}0.33$, $0.54{\pm}0.17$, $0.62{\pm}0.23$, $0.83{\pm0.29}$, $1.03{\pm}0.30$. Conclusion: By comparing and analyzing the differences between $SUV_{bw}$ and $SUV_{bsa}$ in this study, it was found that the differences between $SUV_{bw}$ and $SUV_{bsa}$ increased as patient's BMI increased. Thus, there is room for error in the values of SUV depending on the methods of calculations, and appropriate methods must be applied according to the circumstances in clinical settings.

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Comparative Evaluation of 18F-FDG Brain PET/CT AI Images Obtained Using Generative Adversarial Network (생성적 적대 신경망(Generative Adversarial Network)을 이용하여 획득한 18F-FDG Brain PET/CT 인공지능 영상의 비교평가)

  • Kim, Jong-Wan;Kim, Jung-Yul;Lim, Han-sang;Kim, Jae-sam
    • The Korean Journal of Nuclear Medicine Technology
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    • v.24 no.1
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    • pp.15-19
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    • 2020
  • Purpose Generative Adversarial Network(GAN) is one of deep learning technologies. This is a way to create a real fake image after learning the real image. In this study, after acquiring artificial intelligence images through GAN, We were compared and evaluated with real scan time images. We want to see if these technologies are potentially useful. Materials and Methods 30 patients who underwent 18F-FDG Brain PET/CT scanning at Severance Hospital, were acquired in 15-minute List mode and reconstructed into 1,2,3,4,5 and 15minute images, respectively. 25 out of 30 patients were used as learning images for learning of GAN and 5 patients used as verification images for confirming the learning model. The program was implemented using the Python and Tensorflow frameworks. After learning using the Pix2Pix model of GAN technology, this learning model generated artificial intelligence images. The artificial intelligence image generated in this way were evaluated as Mean Square Error(MSE), Peak Signal to Noise Ratio(PSNR), and Structural Similarity Index(SSIM) with real scan time image. Results The trained model was evaluated with the verification image. As a result, The 15-minute image created by the 5-minute image rather than 1-minute after the start of the scan showed a smaller MSE, and the PSNR and SSIM increased. Conclusion Through this study, it was confirmed that AI imaging technology is applicable. In the future, if these artificial intelligence imaging technologies are applied to nuclear medicine imaging, it will be possible to acquire images even with a short scan time, which can be expected to reduce artifacts caused by patient movement and increase the efficiency of the scanning room.

Research of operators and patients exposed to electromagnetic field in the hospital (병원에서의 환자, 의료진의 전자파 노출 실태 조사)

  • Ji, Hyo-Chul;Hong, Hyun-Ki;Kim, Sung-Woo;Lee, Ju-Hyung;Kim, Deok-Won
    • Proceedings of the KIEE Conference
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    • 2007.04a
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    • pp.70-72
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    • 2007
  • In this study, electromagnetic fields emitted from the various environment in the hospital were measured. Measurement spot was patients' head. To monitor how much magnetic fields are emitting from operation room, monitoring device was attached to 19 anesthesiologist and monitoring lasted 8 hours. We also took a measurement from various medical devices. Devices include ESWL, PET, MRI, CT, Gamma knife, X-ray, Angiogram, Echocardiogram, Upper GI and Linear Accelerator. Electromagnetic fields were measured from 10 spots from each of 5 patient waiting room. As a results, there were no places showing risk of high exposure. All the measurement values were below the reference levels for general public exposure to time varying electric and magnetic fields which is issued by ICNIRP.

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A Study on the Individual Radiation Exposure of Medical Facility Nuclear Workers by Job (의료기관 핵의학 종사자의 직무 별 개인피폭선량에 관한 연구)

  • Kang, Chun-Goo;Oh, Ki-Baek;Park, Hoon-Hee;Oh, Shin-Hyun;Park, Min-Soo;Kim, Jung-Yul;Lee, Jin-Kyu;Na, Soo-Kyung;Kim, Jae-Sam;Lee, Chang-Ho
    • The Korean Journal of Nuclear Medicine Technology
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    • v.14 no.2
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    • pp.9-16
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    • 2010
  • Purpose: With increasing medical use of radiation and radioactive isotopes, there is a need to better manage the risk of radiation exposure. This study aims to grasp and analyze the individual radiation exposure situations of radiation-related workers in a medical facility by specific job, in order to instill awareness of radiation danger and to assist in safety and radiation exposure management for such workers. Materials and Methods: 1 January 2007 to 31 December 2009 to work in medical institutions are classified as radiation workers Nuclear personal radiation dosimeter regularly, continuously administered survey of 40 workers in three years of occupation to target, Imaging Unit beautifully, age, dose sector, job function-related tasks to identify the average annual dose for a deep dose, respectively, were analyzed. The frequency analysis and ANOVA analysis was performed. Results: Imaging Unit beautifully three years the annual dose PET and PET/CT in the work room 11.06~12.62 mSv dose showed the highest, gamma camera injection room 11.72 mSv with a higher average annual dose of occupation by the clinical technicians 8.92 mSv the highest, radiological 7.50 mSv, a nurse 2.61 mSv, the researchers 0.69 mSv, received 0.48 mSv, 0.35 mSv doctors orderly, and detail work employed the average annual dose of the PET and PET/CT work is 12.09 mSv showed the highest radiation dose, gamma camera injection work the 11.72 mSv, gamma camera imaging work 4.92 mSv, treatment and safety management and 2.98 mSv, a nurse working 2.96 mSv, management of 1.72 mSv, work image analysis 0.92 mSv, reading task 0.54 mSv, with receiving 0.51 mSv, 0.29 mSv research work, respectively. Dose sector average annual dose of the study subjects, 15 people (37.5%) than the 1 mSv dose distribution and 5 people (12.5%) and 1.01~5.0 mSv with the dose distribution was less than, 5.01~10.0 mSv in the 14 people (35.0%), 10.01~20.0 mSv in the 6 people (15.0%) of the distribution were analyzed. The average annual dose according to age in occupations that radiological workers 25~34 years old have the highest average of 8.69 mSv dose showed the average annual dose of tenure of 5~9 years in jobs radiation workers in the 9.5 mSv The average was the highest dose. Conclusion: These results suggest that medical radiation workers working in Nuclear Medicine radiation safety management of the majority of the current were carried out in the effectiveness, depending on job characteristics has been found that many differences. However, this requires efforts to minimize radiation exposure, and systematic training for them and for reasonable radiation exposure management system is needed.

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Comparison and evaluation of 89Zr-labeled trastuzumab and Thio-trastuzumab : a potential immuno-PET probe for HER2-positive carcinomas

  • Un Chol Shin;Seoku Bae;Suk-man Kim;Min-Woo Lee;Han Sang Jin;Hyun Park;Kyo Chul Lee;Jung Young Kim;Ji Woong Lee
    • Journal of Radiopharmaceuticals and Molecular Probes
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    • v.7 no.2
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    • pp.105-111
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    • 2021
  • 89Zr is a positron-emitting radioisotope, which has known as well-suited radioisotope for use in a monoclonal antibody-based imaging agent for immuno-PET. The purpose of this study was to quantitatively evaluate the diagnostic ability of general trastuzumab and thio-trastuzumab as HER2 positive receptors based on Df hexadentate iron chelator. Desferrioxamine-p-SCN (Df-Bz-NCS) and desferroixamine-maleimide (Df-Mal) were purchased from Macrocyclics (Dallas, TX, USA). The trastuzumab was purchased from Roche (Schweiz), and thio-trastuzumab was obtained from professor Hyo-Jeong Hong group (Kangwon National University). The radioisotope 89Zr was produced by domestic purification system and KIRAMS using medical cyclotron (50 MeV, Scantronix). The conjugates of Df-trastuzumab and Df-thio-trastuzumab were prepared with Df-Bz-NCS and Df-Mal under basic aqueous solution (pH 8-9) at room temperature, respectively. The conjugates purified by PD-10 column were mixed with dried 89Zr chloride. 89Zr-labeled conjugates were purified and concentrated by Amicon ultra centrifugal filter. The preparation step and time of 89Zr-labeled conjugates was shorted as 4 steps within 2 hours. 89Zr-labeled conjugates showed the highly radiochemical purity of over 98%, and were very stable until 7 days by the analysis of radio-ITLC method. Each radio-labeled conjugates were also exhibited the highly stability in both PBS buffer and mouse serum. Immuno-PET imaging of 89Zr-labeled conjugates in mice bearing gastric cancer xenograft tumors with HER2 expression showed high tumor uptake in the NCI-N87 HER2-expressing. However, 89Zr-Df-Mal-thio-trastuzumab showed a relatively lower tumor-to-background ratio than 89Zr-Df-Bz-trastuzumab, as well as whole-body distribution. In the results, 89Zr-Df-Bz-trastuzumab was evaluated to have a relatively higher HER2 diagnostic ability than 89Zr-Df-Mal-thio-trastuzumab.