• Title/Summary/Keyword: Neutron activation

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Characterization of Korean Archaeological Artifacts by Neutron Activation Analysis (II). Multivariate Classification of Korean Ancient Glass Pieces (중성자 방사화분석에 의한 한국산 고고학적 유물의 특성화 연구 (II). 다변량 해석법에 의한 고대 유리제품의 분류 연구)

  • Chul Lee;Oh Cheun Kwun;Ihn Chong Lee;Nak Bae Kim
    • Journal of the Korean Chemical Society
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    • v.31 no.6
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    • pp.567-575
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    • 1987
  • Fourty five ancient Korean glass pieces have been determined for 19 elements such as Ag, As, Br, Ce, Co, Cr, Eu, Fe, Hf, K, La, Lu, Na, Ru, Sb, Sc, Sm, Th and Zn, and for one such as Pb by instrumental neutron activation analysis and by atomic absorption spectrometry, respectively. The multivariate data have been analyzed for the relation among elemental contents through the variance-covariance matrix. The data have been further analyzed by a principal component mapping method. As the results training set of 5 class have been chosen, based on the spread of sample points in an eigen vector plot and archaeological data. The 5 training set consisting of 36 species and a test set consisting of 9 species bave finally been analyzed for the assignment to certain classes or outliers through the statistical isolinear multiple component analysis (SIMCA). The results have showed the whole species for 5 training set and 3 species in the test set are assigned appropriately and these are in accord with the results by principal component mapping.

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Simultaneous Determination of Mercury, Bromine, Arsenic and Cadmium in Biological Materials by Neutron Activation Analysis

  • Lee, Chul;Kim, Nak-Bae;Park, Euy-Byung
    • Nuclear Engineering and Technology
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    • v.5 no.4
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    • pp.279-285
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    • 1973
  • A method for the simultaneous determination of mercury, bromine, arsenic and cadmium in biological samples is described. Following neutron activation and a simple distillation of volatile compounds, mercury and bromine were determined by gamma-ray spectrometry. Arsenic and cadmium were further separated by cation exchange separation and determined similarly. Determination limits for mercury, bromine, arsenic and cadmium were 0.001$\mu\textrm{g}$, 0.003$\mu\textrm{g}$, 0.001$\mu\textrm{g}$ and 0.02$\mu\textrm{g}$, respectively. The method has been applied to the determination of mercury, bromine, arsenic and cadmium in rice and fish samples. Analysis of a standard kale powder yielded the values of 0.046$\mu\textrm{g}$/g for mercury, 24.5$\mu\textrm{g}$/g for bromine 0.17 $\mu\textrm{g}$/g for arsenic and 0.50$\mu\textrm{g}$/g for cadmium.

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Study on Distribution of Elemental Concentration with a Different Depth of River Sediment using Neutron Activation Analysis (중성자 방사화 분석을 이용한 하천 침전물의 깊이에 따른 원소의 함량분포 연구)

  • Kim, Hyeon-Soo;Im, Hye-Ran;Kim, Yong-Uhn;Moon, Jong-Hwa
    • Analytical Science and Technology
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    • v.16 no.3
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    • pp.232-239
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    • 2003
  • The river sediments were collected from 4 points of Seoknam river, one point of Miho river and one point of the joining area of two rivers. For preparation of sample, three sediment samples were collected for the surface, middle and lower part of the sediment at each sampling point. The elemental concentrations were analyzed by neutron activation analysis using HANARO research reactor at Korea Atomic Energy Research Institute, and the concentrations of 30 elements were determined by the relative method using standard reference material of NIST. As a result of analysis, it was found that when the examination and prediction of contamination distribution about the site where the contamination site of river is connected to the lower river is done, the specific gravity of elements which is contained in the sediment and the speed of a current of river should be considered and also found that when the samples for concentration analysis in the river sediments are collected, for the establishment of regional representatives in samples, the range of sampling depth should be determined considering the specific gravity of elements and the speed of a current.

A provenance study of roof tiles from the late Korea dynasty using Neutron Activation Analysis (중성자 방사화분석에 의한 고려 후기 기와의 산지 연구)

  • Chung, Kwang-Yong;Kim, Myung-Jin
    • Analytical Science and Technology
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    • v.14 no.6
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    • pp.476-485
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    • 2001
  • Both concave and convex roof-end tiles having same style and shape are excavated in Yongjangsung castle at Jindo and Burnhwasa temple at Wando in Jeollanam-Do that are the Sambyulcho's resistance sites against Mongolia in the late Koryo dynasty. Obtained data by NAA have been used to classify the equality of a raw materials' porvenance by multiple correlation analysis(MCA) and discriminant analysis. The results of MCA has shown that there are very high correlation for [La : Sm], and [Lu : Yb]. Exactly pottery site at Chungdo, roof tile site at Chungyang, Yongjangsung castle and Bumhwasa temple and Chunghaejin site at Jangdo were distributed for four trace elements, Cr, Sc, ${\Delta}$(${\Sigma}$(Lu, Yb)) and Eu by discriminant analysis, and their accuracy is above 95%. This means that Yongjangsung castle and Bumhwasa temple have same raw material's provenance.

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Measurements of Neutron Activation and Dose Rate Induced by High-Energy Medical Linear Accelerator

  • Kwon, Na Hye;Jang, Young Jae;Kim, Jinsung;Kim, Kum Bae;Yoo, Jaeryong;Ahn, So Hyun;Kim, Dong Wook;Choi, Sang Hyoun
    • Progress in Medical Physics
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    • v.32 no.4
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    • pp.145-152
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    • 2021
  • Purpose: During the treatments of cancer patients with a linear accelerator (LINAC) using photon beams with energies ≥8 MV, the components inside the LINAC head get activated through the interaction of photonuclear reaction (γ, n) and neutron capture (n, γ). We used spectroscopy and measured the dose rate for the LINAC in operation after the treatment ended. Methods: We performed spectroscopy and dose rate measurements for three units of LINACs with a portable high-purity Germanium (HPGe) detector and a survey meter. The spectra were obtained after the beams were turned off. Spectroscopy was conducted for 3,600 seconds, and the dose rate was measured three times. We identified the radionuclides for each LINAC. Results: According to gamma spectroscopy results, most of the nuclides were short-lived radionuclides with half-lives of 100 days, except for 60Co, 65Zn, and 181W nuclides. The dose rate for three LINACs obtained immediately in front of the crosshair was in the range of 0.113 to 0.129 µSv/h. The maximum and minimum dose rates measured on weekends were 0.097 µSv/h and 0.092 µSv/h, respectively. Compared with the differences in weekday data, there was no significant difference between the data measured on Saturday and Sunday. Conclusions: Most of the detected radionuclides had half-lives <100 days, and the dose rate decreased rapidly. For equipment that primarily used energies ≤10 MV, when the equipment was transferred after at least 10 minutes after shutting it down, it is expected that there will be little effect on the workers' exposure.

The study of elemental depth distribution at the Jinheung catchment sediment core (진흥제 퇴적물 시추코아시료의 깊이별 원소 축적 변화 연구)

  • Yoon, Yoon Yeol;Yang, Dong Yoon;Nahm, Wook Hyun;Cho, Soo Young;Lee, Kil Yong
    • Analytical Science and Technology
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    • v.19 no.1
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    • pp.45-49
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    • 2006
  • Drilled sediment core was acquired from Jinheung catchment which was located at Jeollabuk-do Jeongeup city. Elements concentration variation were studied by neutron activation analysis using sediment core by divided 1 cm depth interval. The concentration of major element such as Na, K were increased but Fe was decrease with depth. Minimum elements concentration and particle size were observed at 17 cm depth. This depth was considered 1969 year which was great dry year recorded from the rain fall data and the sedimentation rate was calculated $0.197g{\cdot}cm^{-2}{\cdot}year^{-1}$.

Electrical characteristics of SiC schottky diodes treated by the various dry etch methods for a damaged surface (변형막 식각 방법에 따른 탄화규소 쇼트키 다이오드의 전기적 특성)

  • Choi, Young-Min;Kang, In-Ho;Bahng, Wook;Joo, Sung-Jae;Kim, Sang-Cheol;Kim, Nam-Kyun;Kim, Sung-Jin
    • Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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    • 2008.06a
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    • pp.232-233
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    • 2008
  • The 4H-SiC schottky diodes treated by the various dry etch methods were fabricated and electrically characterized. The post etch process including an Inductively Coupled Plasma(ICP) etch and a Neutron Beam Etch(NBE) was performed after a high-temperature activation annealing without graphite cap in order to eliminate the damaged surface generated during the activation annealing. The reverse leakage current of diode treated by ICP was 1/35 times lower than that of the diode without any post etch at the anode bias of -100V, while the reverse leakage current of diode treated by NBE was 1/44 times lower at the same bias.

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Simulation of the Determination of NaCl Concentration in Concrete samples by the Neutron induced Prompt Gamma-ray Method

  • Kim, Hyeon-Soo
    • Journal of Environmental Science International
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    • v.13 no.2
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    • pp.175-180
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    • 2004
  • A prompt gamma-ray neutron activation (PGNA) system was simulated by the Monte Carlo N-Particle transport code (MCNP-4A) to estimate the level at which the scattered photon fluence rate, the absolute efficiency of the HPGe-detector, the volume of the concrete sample and the $^{35}$ /Cl(n, ${\gamma}$) reaction rate in this sample contribute to the count rate in the NaCl concentration measurement. The n- ${\gamma}$ fluence rates at the ST-2 beam tube exit of the HANARO reactor were used as input data, and the GAMMA-X type HPGe detector was modeled to tally 1.1649 MeV ${\gamma}$ -rays emitted from the $^{35}$ Cl(n, ${\gamma}$) reaction in the concrete sample. For three cylindrical concrete samples of 13.8, 46.8 and 157.1 ㎤ volumes, respectively, the relations between the NaCl weight fractions of 0.1, 1, 2 and 5 % in each of the concrete samples and the 1.1 649 MeV pulses created in the HPGe detector model were studied. As a result, it was found that the count rate at the same NaCl concentration nearly depends on the volume of the samples in a simulated condition of the same NaCl concentration samples, and that the linearities of the NaCl concentration calibration curves were reasonable in the narrow range of the NaCl weight fraction.

A Study on the Radioactive Products of Components in Proton Accelerator on Short Term Usage Using Computed Simulation (몬테칼로 시뮬레이션을 활용한 양성자가속기 단기사용 시 구성품의 방사화 평가)

  • Bae, Sang-Il;Kim, Jung-Hoon
    • Journal of radiological science and technology
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    • v.43 no.5
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    • pp.389-395
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    • 2020
  • The evaluation of radioactivated components of heavy-ion accelerator facilities affects the safety of radiation management and the exposure dose for workers. and this is an important issue when predicting the disposal cost of waste during maintenance and dismantling of accelerator facilities. In this study, the FLUKA code was used to simulate the proton treatment device nozzle and classify the radio-nuclides and total radioactivity generated by each component over a short period of time. The source term was evaluated using NIST reference beam data, and the neutron flux generated for each component was calculated using the evaluated beam data. Radioactive isotopes caused by generated neutrons were compared and evaluated using nuclide information from the International Radiation Protection Association and the Korea Radioisotope association. Most of the nuclides produced form of beta rays and electron capture, and short-lived nuclides dominated. However, In the case of 54Mn, which is a radioactive product of iron, the effect of gamma rays should be considered. In the case of tritium generated from a material with a low atomic number, it is considered that handling care should be taken due to its long half-life.

Estimation of nuclear heating by delayed gamma rays from radioactive structural materials of HANARO

  • Noh, Tae-yang;Park, Byung-Gun;Kim, Myong-Seop
    • Nuclear Engineering and Technology
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    • v.50 no.3
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    • pp.446-452
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    • 2018
  • To improve the accuracy and safety of irradiation tests in High flux Advanced Neutron Application ReactOr (HANARO), the nuclear energy deposition rate, which is called nuclear heating, was estimated for an irradiation capsule with an iridium sample in the irradiation hole in order. The gamma rays emitted from the radioisotopes (RIs) of the structural materials such as flow tubes of fuel assemblies and heavy water reflector tank were considered as radiation source. Using the ORIGEN2.1 code, emission rates of delayed gamma rays were calculated in consideration of the activation procedure for 8 years and 2 months of HANARO operation. Calculated emission rates were used as a source term of delayed gamma rays in the MCNP6 code. By using the MCNP code, the nuclear heating rates of the irradiation capsules in the inner core, outer core, and heavy water reflector tank were estimated. Calculated nuclear heating in the inner core, outer core, and heavy water reflector tank were 200-260 mW, 80-100 mW, and 10 mW, respectively.