• Title/Summary/Keyword: Neutron activation method

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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.

Analysis of Radioactive Characterization in the Medical Linear Accelerator Shielding Wall Using Monte Carlo Method (몬테칼로법을 이용한 의료용 선형가속기 차폐벽의 방사화 특성 분석)

  • Lee, Dong-Yeon;Park, Eun-Tae
    • The Journal of the Korea Contents Association
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    • v.16 no.10
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    • pp.758-765
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    • 2016
  • This study analyzed for the radioactive shielding wall, which shields the medical linear accelerator. This allows to evaluate the level of waste with respect to the shield wall, which accounts for more than half of the cost of dismantling later linac facility. In addition, by analyzing the waste processing method according we discuss the way to obtain the benefits in terms of dismantling cost. Results of the simulate, the amount sufficient to screen the amount of neutron radiation occurring in the shielding wall linac was measured. And neutron activation analysis results were analyzed nuclides more than about 20. This analysis was in excess of that, $^{24}Na$, $^{45}Ca$, $^{59}Fe$ nucleus paper deregulation concentration. The value is reduced is greater the deeper the depth of the shielding wall concentration. Based on this, three specific areas (E, F, G) was estimated to be impossible to landfill or recycling. The rest area was estimated to be buried or recycled if possible more than a predetermined depth.

Neutron Activation Analysis of Human Hair for Human Health Assessment (인체보건 환경평가를 위한 모발의 중성자방사화분석)

  • Chung, Young-Sam;Kang, Sang-Hoon;Moon, Jong-Hwa;Kang, Young Hwan;Cho, Seung-Yon
    • Analytical Science and Technology
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    • v.14 no.2
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    • pp.131-139
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    • 2001
  • There is personal difference in the concentrations of trace elements in human hair according to human life or history suck as occupation, race, sex, age, food habit, social condition and so on. It is also found that the individual's deviation of elemental concentrations is reflecting the degree of environmental pollutants exposure to human body, intakes of food and metabolism. To compare the degree of accumulation in the hair tissue, human hair samples were collected from five positions of head and analyzed by non-destructive neutron activation analysis with and without washing according to IAEA's recommended method. Analytical quality control is performed using the certified reference material. The relative error of Cu, Cr, Na, Co, Mg, As, Se, Zn and those of Mn, Ca, Fe, Sr are within ${\pm}5%$ and ${\pm}10%$, respectively and the relative standard deviation of elements are within ${\pm}10%$. The deviations between the individuals and hair sampling positions were estimated. The deviation of individual was seven times more than that of positions. Under the defined condition, the difference and the correlation of elemental concentrations were compared with two different groups, office and factory workers. The result can be used as a fundamental data for human health and environment assessment.

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Application of Pulse Pile-Up Correction Spectrum to the Library Least-Squares Method (펄스 중첩 보정 스펙트럼의 라이브러리 최소자승법에의 이용)

  • Lee, Sang-Hoon
    • Journal of Radiation Protection and Research
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    • v.31 no.4
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    • pp.173-179
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    • 2006
  • The Monte Carlo simulation code CEARPPU has been developed and updated to provide pulse pile-up correction spectra for high counting rate cases. For neutron activation analysis, CEARPPU correction spectra were used in library least-squares method to give better isotopic activity results than the convention library least-squares fitting with uncorrected spectra.

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 Provenance of the 5th Century Jar Coffin using Neutron Activation Analysis (중성자 방사화분석에 의한 5세기 옹관의 산지 연구)

  • Chung, Kwang-Yong
    • Journal of Conservation Science
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    • v.26 no.4
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    • pp.459-465
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    • 2010
  • The 5th century kiln that produced pottery coffins was found for the first time in Korea, located in the Oryang-dong remains in the city of Naju. This kiln, located in the central area of the Yeongsan River, provides important data for research on mortuary practices in prehistoric society, including the structure of production and patterns of distribution and consumption. For this study, the remains of five ancient tombs and pottery coffins excavated from the 4th century Mandong archaeological site were chosen to determine the area of consumption of pottery coffins produced at the Oryang-dong kiln. The samples from each area of remains were analyzed for minor elements using neutron activation analysis method, and from these results, the identities of the corresponding production areas were investigated using the multi-variant statistical analysis of discriminant analysis. The evidence strongly suggests that pottery coffins produced at the Oryang-dong kiln in Naju were used in ancient tombs of the Bannam mound in Naju, the Okyari mound in Yeongam, and the Banam mound in Hampyeong, reaching those sites through trade and distribution. The findings also suggest that pottery coffins from the Mandong archeological site in Gochang and the Inpyeong mound in Muan were not produced at the Oryang-dong kiln in Naju, but rather were brought from pottery kilns in different production areas, through trade and distribution.

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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Neutron Activation Analysis of Korean Clays and Pottery

  • Lee Chul;Kwun Oh Cheun;Kim Nak Bae;Lee Ihn Chong
    • Bulletin of the Korean Chemical Society
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    • v.6 no.4
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    • pp.241-246
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    • 1985
  • Twenty trace elements were determined in 250 Korean potsherds and 5 clay samples by instrumental NAA. In the absence of identified samples of known origin, the potsherds were classified by a hierarchical centroid sorting method to construct a dendrogram. From this dendrogram 61 well-defined samples were selected to form 8 subclasses and five elements such as Cr, Cs, Sm, Sc and Th were supposed to be the main contributors for the classification. The 61 samples along with 5 clay samples were reclassified by means of minimal spanning tree as well as the hierarchical centroid sorting method by using 5 elements selected. As the results, the potsherds of certain classes defined in this work could be taken as a basis for latter identification and served as batches of identified species.

A New Method of Determination for the Trace Ruthenium in High Purity Palladium by Neutron Activation Analysis (방사화 분석에 의한 고순도 팔라듐 금속중의 미량 루테늄에 관한 새로운 정량법)

  • Lee, Chul;Yim, Yung-Chang;Uhm, Kyung-Ja;Chung, Koo-Soon
    • Journal of the Korean Chemical Society
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    • v.15 no.4
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    • pp.191-197
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    • 1971
  • Ruthenium content in highly purified palladium metal (99.9%) was determined by counting $^{105}Rh$ nuclide which was produced by $^{104}Ru(n,{\gamma};{\beta}^-)^{105}Rh$ nuclear reaction. Palladium sample and ruthenium standard were irradiated by neutron with the Pneumatic Transfer System of TRIGA MARK II reactor. Palladium and ruthenium were dissolved by treating with aqua-regia and by fusing with sodium peroxide flux respectively. $^{105}Rh$ was separated through anion and cation exchange resin columns. The ruthenium content was determined by comparing the $^{105}Rh$ activities, obtained from the palladium sample, with that from pure ruthenium standard. The detection limit of ruthenium by the present method is about 1 ppm of ruthenium in 10 mg of palladium, which is approximately 40 times more sensitive than that of the conventional radioactivation method which employs $^{102}Ru(n,{\gamma})^{103}Ru$ nuclear reaction.

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Determination of volatile and residual iodine during the dissolution of spent nuclear fuel (사용 후 핵연료 용해 중 휘발 및 잔류 요오드 분석)

  • Kim, Jung Suk;Park, Soon Dal;Jeon, Young Shin;Ha, Young Keong;Song, Kyuseok
    • Analytical Science and Technology
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    • v.22 no.5
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    • pp.395-406
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    • 2009
  • The determination of iodine in the spent nuclear fuel and the volatile behavior during its acid dissolution have been studied by NAA(neutron activation analysis) and electron probe microanalysis (EPMA). Simulated spent fuels (SIMFUELs) were dissolved in $HNO_3$(1+1) at $90^{\circ}C$ for 8 hours. The iodine remained in a dissolver solution after dissolution, and that condensed in dissolution apparatus and trapped in the adsorbent by volatilization during the dissolution were determined, respectively. The condensed iodine was recovered by the redistillation with $HNO_3$(1+1) after transfer of the dissolver solution. The iodines in the dissolver and redistilled solution were separated by solvent extraction followed by ion exchange or precipitation method and determined by RNAA (radiochemical neutron activation analysis). The ion exchange column and filtration kit used for the isolation of iodine, which were prepared with a polyethylene tube, were used as an insert in the pneumatic tube for neutron irradiation. The iodine volatilized during the dissolution of SIMFUELs was collected in a trapping tube containing Ag-silica gel (Ag-impregnated silica gel) adsorbent, and the distribution of iodine trapped in the adsorbents were determined by EPMA. The adsorbing characteristics shown with the SIMFUELs were compared with those shown with a real spent fuel from the nuclear power plant.