• Title/Summary/Keyword: 감마방출핵종

Search Result 52, Processing Time 0.02 seconds

Investigation on the techniques of quality control for radiation counting systems (방사선 측정기의 품질관리 기법에 대한 고찰)

  • Song, Byoung-Chul;Kim, Young-Bok;Han, Sun-Ho;Oh, Se-Jin;Lee, Myung-Ho;Song, Kyu-Seok
    • Analytical Science and Technology
    • /
    • v.24 no.6
    • /
    • pp.414-420
    • /
    • 2011
  • In this study, radiation measurement system has been investigated to set up for the radioisotopes analysis in the radioactive waste samples after selecting the radiation counters of alpha beta and gamma nuclides. The counting efficiencies for alpha, beta and gamma measurement systems were calibrated. To obtain stability of the radiation detectors, quality control program has been established. Also, minimum detectable activities (MDAs) depending on the type of samples were calculated for increasing the confidence level for analytical result.

Study on the Measurement of Radon concentrations in soil samples using γ-spectrometer (γ-spectrometer를 이용한 토양시료의 라돈농도 측정법에 관한 연구)

  • Kang, Sunga;Lee, Sangsoo;Choi, Guirack;Lee, Junhaeng
    • Journal of the Korean Society of Radiology
    • /
    • v.7 no.1
    • /
    • pp.31-36
    • /
    • 2013
  • The radioactive gas radon ($^{222}Rn$), which is generated from the decay process of uranium ($^{238}U$) originating from the soil of more than 85 percent higher the porosity of the soil, the soil can radiate out the possibility that many isotopes. In order to protect the human body from radon, above all, the development of accurate measurement techniques to formulate appropriate measures should be followed. This study Gamma-ray spectrometry using a high purity germanium (HPGe) detector, if you want to measure radon unstable the nature radiation of the background problems can be reduced, radium and radon daughter nuclides after radioactive equilibrium leads to Radon concentration was measured, the soil samples from the Gamma-ray emitting nuclides, and the energy spectrum is analyzed.

Effect of Gamma Energy of Positron Emission Radionuclide on X-Ray CT Image (양전자 방출 핵종(18F)의 감마에너지가 X선 CT영상에 미치는 영향)

  • Kim, Gha-Jung;Bae, Seok-Hwan;Kim, Ki-Jin;Oh, Hye-Kyong
    • 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.

Relative Efficiency Determination of HPGe Detector (HPGe 검출기의 상대효율 결정)

  • 강정구;김승곤;김종일;이정옥;이춘호;최재우
    • Progress in Medical Physics
    • /
    • v.4 no.2
    • /
    • pp.27-36
    • /
    • 1993
  • A relative efficiency of a HPGe detector as a function of the incident gamma ray energy in the range 120 keV to 1500 keV was measured using 21 gamma rays emitted by a $\^$152/Eu source. A semiempirical expression was then determined which can reproduce the measured values reasonably well. The two results are compared to a Monte Carlo simulation calculation.

  • PDF

A Study on the Nuclear Structure through the Multipurpose Coincidence Measurement System Development ( I ) - The Electromagnetic Properties of the Gamma Transitions in $^{75}As$- (다목적 동시측정 장치 개발에 의한 원자핵 구조 연구(I) - $^{75}As$의 감마 전이에 대한 전자기적 특성 -)

  • Chung, Won-Mo;Chung, Kap-Soo;Joo, Koan-Sik;Na, Sang-Kyun;Hwang, Han-Yull
    • Journal of Radiation Protection and Research
    • /
    • v.18 no.1
    • /
    • pp.53-61
    • /
    • 1993
  • The gamma-gamma coincidence measurements and angular correlation measurement associated with the electron capture of $^{75}Se$ have been carried to understand the structure for the odd nuclei $^{75}As$ with two HPGe detectors. As a result, we could determined the band structure of 5/2 state to be of 1/2 [310] band which is based on $f_{5/2}$ proton state. Also we obtained the multipole admixture in the state of 279.5keV by using the mixing ratios of $121.1{\sim}279.5keV$ cascade. Subsequently, it is determined that 25.56% electric quadrupole transition is involved in the state of 279.5keV.

  • PDF

Study on the cascade summing correction for high efficiency HPGe detector (고효율 HPGe 검출기의 동시합성효과 보정 연구)

  • Lee, M.S.
    • Journal of Radiation Protection and Research
    • /
    • v.30 no.3
    • /
    • pp.107-112
    • /
    • 2005
  • Cascade summing occurs when two gamma-rays emitted in the decay of a single nucleus both deposit energy in a detector. The effect may cause systematic errors that can reach levels of more than ten percent for some radionuclides. A method for estimation of the effect of these coincidences was developed. It is based on direct computation of the effect by means of peak to total ratio measured for the place around the detector. It has been shown that the P/T ratio for the given energy in the working space around the detector may not be a constant value and must use its mean value. Some results from a peak to total calibration study in the presence of scattering materials are also given.

Assessment of Effective Doses in the Radiation Field of Contaminated Ground Surface by Monte Carlo Simulation (몬테칼로 시뮬레이션에 의한 지표면 오염 방사선장에서의 유효선량 평가)

  • Chang, Jai-Kwon;Lee, Jai-Ki;Chang, Si-Young
    • Journal of Radiation Protection and Research
    • /
    • v.24 no.4
    • /
    • pp.205-213
    • /
    • 1999
  • Effective dose conversion coefficients from unit activity radionuclides contaminated on the ground surface were calculated by using MCNP4A rode and male/female anthropomorphic phantoms. The simulation calculations were made for 19 energy points in the range of 40 keV to 10 MeV. The effective doses E resulting from unit source intensity for different energy were compared to the effective dose equivalent $H_E$ of previous studies. Our E values are lower by 30% at low energy than the $H_E$ values given in the Federal Guidance Report of USEPA. The effective dose response functions derived by polynomial fitting of the energy-effective dose relationship are as follows: $f({\varepsilon})[fSv\;m^2]=\;0.0634\;+\;0.727{\varepsilon}-0.0520{\varepsilon}^2+0.00247{\varepsilon}^3,\;where\;{\varepsilon}$ is the gamma energy in MeV. Using the response function and the radionuclide decay data given in ICRP 38, the effective dose conversion coefficients for unit activity contamination on the ground surface were calculated with addition of the skin dose contribution of beta particles determined by use of the DOSEFACTOR code. The conversion coefficients for 90 important radionuclides were evaluated and tabulated. Comparison with the existing data showed that a significant underestimates could be resulted when the old conversion coefficients were used, especially for the nuclides emitting low energy photons or high energy beta particles.

  • PDF

Study of occupational exposure in PET/CT (PET/CT 종사자의 방사선피폭에 관한 연구)

  • Na, Soo-Kyung;Park, Byung-Sub;Kang, Yong-Gil
    • 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($^{18}F$).

Development of Effective ${\gamma}$-ray and ${\beta}$-ray Detection Methods For Low-Level Radioactive Wastes (극저준위 방사성 폐기물을 위한 효율적인 ${\gamma}$-선 및 ${\beta}$-선 측정 방법 개발)

  • Kwak, Sung-Woo;Yeom, Yu-Sun;Kim, Ho-Kyung;Cho, Gyu-Seong;Park, Joo-Wan;Kim, Chang-Lak;Song, Myung-Jae
    • Journal of Radiation Protection and Research
    • /
    • v.26 no.4
    • /
    • pp.393-398
    • /
    • 2001
  • The non-combustible RI wastes disposed of in hospital every year emit ${\gamma}$-ray or ${\beta}$-ray but their activities are very low to the extent of background. Development of more simple methods is needed because the conventional detection methods are so ineffective and complex. In this study, to solve this problem, detection method using efficiency curve for ${\gamma}$-ray emitting radioactive wastes measurement is proposed and experimental detection efficiency equation is also determined through HPGe's standard specimen measurement. For ${\beta}$-emitting radioisotopes detection, new measurement method using detection efficiency estimated by Monte Carlo simulation and SBD measurements is also proposed. According to the results of this paper, the unknown activity of low-level radioactive wastes without LSC requiring the preparation of standard sample and measurement for standard source detection efficiency could be determined efficiently and simply about ${\pm}17%$ in errors by using the theoretical detection efficiency and the SBD measurement result.

  • PDF

Development of a High Resolution SPECT Detector with Depth-encoding Capability for Multi-energy Imaging: Monte Carlo Simulation (다중에너지 영상 획득을 위한 Depth-Encoding 고분해능 단일광자단층촬영 검출기 개발: 몬테칼로 시뮬레이션 연구)

  • Beak, Cheol-Ha;Hwang, Ji-Yeon;Lee, Seung-Jae;Chung, Yong-Hyun
    • Progress in Medical Physics
    • /
    • v.21 no.1
    • /
    • pp.93-98
    • /
    • 2010
  • The aim of this work was to establish the methodology for event positioning by measuring depth of interaction (DOI) information and to evaluate the system sensitivity and spatial resolution of the new detector for I-125 and Tc-99m imaging. For this purpose, a Monte Carlo simulation tool, DETECT2000 and GATE were used to model the energy deposition and light distribution in the detector and to validate this approach. Our proposed detector module consists of a monolithic CsI(Tl) crystal with dimensions of $50.0{\times}50.0{\times}3.0\;mm^3$. The results of simulation demonstrated that the resolution is less than 1.5 mm for both I-125 and Tc-99m. The main advantage of the proposed detector module is that by using 3 mm thick CsI(Tl) with maximum-likelihood position-estimation (MLPE) method, high resolution I-125 imaging and high sensitivity Tc-99m imaging are possible. In this paper, we proved that our new detector to be a reliable design as a detector for a multi-energy SPECT.