• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05a
• /
• pp.157-162
• /
• 1998

양전자 단층 촬영장치(PET)에 사용되는 주요 양전자 방출 핵종들의 생성 단면적을 평가하였다. 평가한 생성 반응들은 $^{14}$ N(p,$\alpha$)$^{11}$ C,$^{16}$ O(p,$\alpha$)$^{13}$N, $^{14}$ N(d,n)$^{15}$ O,$^{18}$ O(p,n)$^{18}$ F,$^{20}$ Ne(d,$\alpha$)$_{18}$ F 이며, 입사 입자의 에너지 범위는 반응 문턱 에너지부터 약 150 MeV까지이다. 또한 하전입자 범 모니터용 표준 단면적으로서 $^{27}$ Al에 d 및 $^3$He, $\alpha$가 반응하여 $^{22}$ Na가 생성되는 반응의 단면적들을 입사 에너지 약 120 MeV까지 평가하였다. 실험치를 fitting하게나 ALICE95 코드를 이용하여 이론적 계산을 수행하였는데, 평가 단면적의 표준 편차는 10-30%이다 이들 평가 단면적들은 가속기를 이용한 PET용 핵종의 생산율 계산 및 빔 모니터의 표준 단면적으로 사용하기에 적절한 것으로 판단된다.

• Journal of the Korea Academia-Industrial cooperation Society
• /
• v.12 no.10
• /
• pp.4418-4424
• /
• 2011

This study is aimed to assess the effect of the gamma ray of 511keV energy which is emitted from phantom where the positron emission radionuclide was injected on X-ray CT image. As a scanning method, the CT number and pixel value of the reference image where water was injected(0 mCi), and those acquired by changing the capacity of 18F(Fluorine), positron emission radionuclide, into 1 mCi, 2 mCi, 5 mCi, and 10 mCi were measured. As a result of measuring the CT number(HU) of the phantom image where the positron emission radionuclide($^{18}F$) was injected, there were reference water ($-7.58{\pm}0.66$ HU), 1 mCi($-9.85{\pm}0.50$ HU), 2 mCi($-10.27{\pm}0.21$ HU), 5 mCi($-11.31{\pm}0.66$ HU), and 10 mCi($-13.47{\pm}0.38$ HU). Compared with the image where it was filled with water, there was a reduction of 5.89 Hu in 10 mCi, 3.73 in 5 mCi, 2.69 HU in 2 mCi, and 2 HU in 1 mCi. As for the pixel value of the phantom image, there were reference water ($-2.70{\pm}0.75$), 1 mCi($-4.72{\pm}0.58$), 2 mCi($-6.01{\pm}0.78$), 5 mCi($-6.10{\pm}0.84$), and 10 mCi($-8.20{\pm}0.60$). Compared with the reference image, there was a reduction of 5.50 in 10 mCi, 3.40 in 5 mCi, 3.10 in 2 mCi, and 2.02 in 1 mCi. Through this experiment, it was indicated that, with the increase in the dose of the positron emission radionuclide($^{18}F$), the CT number and the pixel value of the image reduced proportionally, and the width of reduction showed a similar value, too. Accordingly, according to the degree of change in X-ray CT image due to the positron emission radionuclide in the quality control item of PET/CT, the proper standard should be established and it should be periodically managed.

• Journal of the Korean Society of Radiology
• /
• v.15 no.6
• /
• pp.849-853
• /
• 2021

PET images used in medical diagnoses are created using positron emitting radionuclides. The radiation used for imaging is generated at 0.511 MeV by p-annihilation. The CSDA range is the distance the particle radiation flew physically, and it is different from the range shown in PET images. This study proposes a novel method that uses radiological criteria to measure this range. The experiment was conducted by applying the MCNP6 simulation to positron emitting nuclides ¹⁸F, ¹¹C, ¹³N, and ¹⁵O. Radiological criteria were based on the location of the p-annihilation event, which is also the image signal. Results showed the radiological range of positrons to be 2.3, 3.9, 5.0, and 7.9 mm for ¹⁸F, ¹¹C, ¹³N, and ¹⁵O, respectively. The higher the positron energy, the larger its difference from the CSDA range. Positron emitting nuclide is being developed and studied as a nuclide for dosimetry or radiotherapy. Further research needs to be conducted into various positron ranges.

• 대한방사선방어학회:학술대회논문집
• /
• 2009.11a
• /
• pp.44-45
• /
• 2009

• 대한방사선방어학회:학술대회논문집
• /
• 2009.04a
• /
• pp.220-221
• /
• 2009

• Journal of Digital Convergence
• /
• v.10 no.11
• /
• pp.449-457
• /
• 2012

The purpose of this study is to investigate the relationship between radiation origin and health professionals, and to reduce exposed dose of radiation through efficient management. Increasing exposed dose of radiation to health professionals are caused by the increase of PET/CT use and a radioactive isotope. Hence, in this study, space dose from each origin of radiation generating was analyzed and the use of personnel protective clothing and shields was compared. As a result of this study, we confirmed that the exposed dose of radiation was much higher in case of wearing personnel protective clothing(0.5 mm pb) than no wearing personnel protective clothing under high energy gamma radiation(511 keV) of the position emitter($^{18}F$).

• Journal of the Korean Society of Radiology
• /
• v.12 no.1
• /
• pp.1-7
• /
• 2018

$^{68}Ga$ was eluted from a $^{68}Ge/^{68}Ga$ radionuclide generator. $^{68}Ga$ decays into $^{68}Zn$, with a half life=67.8min. The decay is 88.9 % by ${\beta}$+ and 11.1 % by EC. The main ${\beta}$+ decay (87.7 %) is to the ground level of $^{68}Zn$ and it is a pure positron emission branch. A small fraction decays ${\beta}$+ (1.2 %) into an excited level of $^{68}Zn$, which promptly decays into the ground level with a ${\gamma}$ (1.077 Mev). This can constitute prompt gamma contamination in the PET data, if the 1.077 Mev ${\gamma}$ has a scatter interaction in the patient, and generates a lower energy ${\gamma}$ in coincidence with the positron annihilation pair. The purpose of this study was to evaluate standardized uptake value(SUV) before and after applying prompt gamma rays correction on $^{68}Ga$-DOTATOC PET/CT image. Fifty patient underwent PET/CT 1 hour after injection of the $^{68}Ga$-DOTATOC. The SUVmax and SUVmean of lesions and normal tissues (Pituitary, Lung, Liver, Spleen, Kidney, Intestine) were evaluated before and after applying prompt gamma correction on $^{68}Ga$-DOTATOC PET/CT image. Additionally, the SUVmax of each lesions and SUVmean of the soft tissues were measured on images. and target to background ratios (TBR) were calculated as quantitative indices. Among 15 patients, 25 of lesions (Pancreas, Liver, Thoracic Spine, Brain) with increased uptake on $^{68}Ga$-DOTATOC PET/CT image. SUVmax and SUVmean were increased in lesion site and normal tissue after prompt gamma rays correction. TBR was $51.51{\pm}49.28$ and $55.50{\pm}53.12$ before and after prompt gamma rays correction, respectively. (p<0.0001)

• The Korean Journal of Nuclear Medicine Technology
• /
• v.13 no.3
• /
• pp.123-131
• /
• 2009

Purpose: We tested a sample of nuclear medicine workers at Korean healthcare institutions for internal contamination with radioactive isotopes, measuring concentrations and evaluating doses of individual exposure. Materials and Methods: The detection and measurement was performed on urine samples collected from 25 nuclear medicine workers at three large hospitals located in Seoul. Urine samples were collected once a week, 100~200 mL samples were gathered up to 6~10 times weekly. A high-purity germanium detector was used to measure gamma radiations in urine samples for the presence of radioactive isotopes. Based on the detection results, we estimated the amounts of intake and committed effective doses using IMBA software. In cases where committed effective doses could not be adequately evaluated with IMBA software, we estimated individual committed effective doses for radionuclides with a very short half life such as $^{99m}Tc$ and $^{123}I$, using the methods recommended by International Atomic Energy Agency. Results: Radionuclides detected through the analysis of urine samples included $^{99m}Tc$, $^{123}I$, $^{131}I$ and $^{201}Tl$, as well as $^{18}F$, a nuclide used in Positron Emission Tomography examinations. The committed effective doses, calculated based on the radionuclide concentrations in urine samples, ranged from 0 to 5 mSv, but were, in the majority of cases, less than 1 mSv. The committed effective dose exceeded 1 mSv in three of the samples, and all three were workers directly handling radioactive sources. No nurses were found to have a committed effective dose in excess of 1 mSv. Conclusions: To improve the accuracy of results, it may be necessary to conduct a long-term study, performed over a time span wide enough to allow the clear determination of the influence of seasonal factors. A larger sample should also help increase the reliability of results. However, as most Korean nuclear medicine workers are currently not necessary to monitored routinely for internal contamination with radionuclides. Notwithstanding, a continuous effort is recommended to reduce any unnecessary exposure to radioactive substances, even if in inconsequential amounts, by regularly surveying workplace environments and frequently monitoring atmospheric concentrations of radionuclides.

• Journal of radiological science and technology
• /
• v.41 no.4
• /
• pp.321-327
• /
• 2018

The purpose of this study is to compare PET imaging performance with Fluorine-18 ($^{18}F$) and Gallium-68 ($^{68}Ga$) for influence of physical properties of PET tracer. Measurement were performed on a Siemens Biograph mCT64 PET/CT scanner using NEMA IEC body phantom and Flangeless Esser PET phantom containing filled with $^{18}F$ and $^{68}Ga$. Emission scan duration(ESD) was set to 1, 2, 3, 4 and 5min/bed for $^{68}Ga$ and 1min/bed for $^{18}F$. The PET image were evaluated in terms of contrast, spatial resolution. Under same condition, The percentage of contrast recovery measured in the phantom ranged from 16.88% to 72.56% for $^{68}Ga$ and from 27.51% to 74.43% for $^{18}F$ and The FWHM value to evaluate spatial resolution was 10.96 mm for $^{68}Ga$ and 9.19 mm for $^{18}F$. For this study, $^{18}F$ produces better image contrast and spatial resolution than $^{68}Ga$ due to higher positron yield and lower positron energy ($^{18}F$: 96.86%, 633.5 keV, $^{68}Ga$: 88.9%, 1899 keV), The physical properties of PET tracer effect on the PET image. $^{68}Ga$ image applying ESD of 3, 4, 5min/bed were showed similar to $^{18}F$ image with ESD of 1min/bed. This study suggests that increasing ESD for acquiring $^{68}Ga$ PET image seem to be similar to $^{18}F$ image.

• The Korean Journal of Nuclear Medicine
• /
• v.33 no.6
• /
• pp.527-536
• /
• 1999

Purpose: Radiotracers that bind to the central benzodiazepine receptor are useful for the investigation of various neurological and psychiatric diseases. [C-11]Flumazenil, a benzodiazepine antagonist, is the most widely used radioligand for central benzodiazepine receptor imaging by PET. We synthesized 3-(2-[F-18]fluoro)flumazenil, a new fluorine-18 ($t_{1/2}$= 110 min) labeled analogue of benzodiazepine receptor imaging agent, and evaluated in vivo for biodistribution in mice. Materials and Methods: Flumazenil (Ro 15-1788) was synthesized by a modification of the reported method. Precursor of 3-(2-[F-18]fluoro)flumazenil, the tosylated flumazenil derivative was prepared by the tosylation of the ethyl ester by ditosylethane. [F-18] labeling of tosyl substitued flumazenil precursor was performed by adding F-18 ion at $85^{\circ}C$ in the hot ceil for 20 min. The reaction mixture was trapped by C18 cartridge, washed with 10% ethanol, and eluted by 40% ethanol. Bidistribution in mice was determined after intravenous injection. Results: The total chemical yield of tosylated flumazenil derivative was ${\sim}40%$. The efficiency of labeling 3-(2-[F-18]fluoro)flumazenil was 66% with a total synthesis time of 50 min. Brain uptakes of 3-(2-[F-18]fluoro)flumazenil at 10, 30, 60 min after injection, were $2.5{\pm}0.37,\;2.2{\pm}0.26,\;2.1{\pm}0.11$ and blood activities were $3.7{\pm}0.43,\;3.3{\pm}0.07,\;3.3{\pm}0.09%ID/g$, respectively. Conclusion: We synthesized a tosylated flumazenil derivative which was successfully labeled with no-carrier-added F-18 by nucleophilic substitution.