• Title/Summary/Keyword: Neutron Activation Analysis

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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.

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.

Research on the optimization method for PGNAA system design based on Signal-to-Noise Ratio evaluation

  • Li, JiaTong;Jia, WenBao;Hei, DaQian;Yao, Zeen;Cheng, Can
    • Nuclear Engineering and Technology
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    • v.54 no.6
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    • pp.2221-2229
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    • 2022
  • In this research, for improving the measurement performance of Prompt Gamma-ray Neutron Activation Analysis (PGNAA) set-up, a new optimization method for set-up design was proposed and investigated. At first, the calculation method for Signal-to-Noise Ratio (SNR) was proposed. Since the SNR could be calculated and quantified accurately, the SNR was chosen as the evaluation parameter in the new optimization method. For discussing the feasibility of the SNR optimization method, two kinds of PGNAA set-ups were designed in the MCNP code, based on the SNR optimization method and the previous signal optimization method, respectively. Meanwhile, the single element spectra analysis method was proposed, and the analysis effect of single element spectra as well as element sensitivity were used for comparing the measurement performance. Since the simulation results showed the better measurement performance of set-up designed by SNR optimization method, the experimental set-ups were built for the further testing, finally demonstrating the feasibility of the SNR optimization method for PGNAA setup design.

Monitoring of Trace Elements and Airborne Particulates in Taejon Areas using Neutron Activation Analysis and Gent Air Sampler (Gent Air Sampler와 중성자방사화분석을 이용한 대전지역의 대기분진중 미량금속 측정연구)

  • 정용삼;문종화;김선하;백성열;박광원
    • Proceedings of the Korea Air Pollution Research Association Conference
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    • 2000.04a
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    • pp.330-332
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    • 2000
  • 삶의 질 향상을 위한 쾌적한 대기환경의 관리 유지는 우리 모두의 관심사중의 하나이다. 호흡기관을 통해 인체내로 흡입되는 $PM_{10}$ 대기분진은 자연적이고 인위적인 발생원에 의해 다양한 미량원소들을 함유하고 있기 때문에 흔히 환경영향 평가를 위한 대기관측시료로 이용되고 있으며, 특히 $PM_{2.5}$ 분진의 질량농도(TSPM)나 원소의 농도가 높을 때 장.단기적으로 인체 보건에 큰 영향을 미치는 것으로 알려져 있다. (중략)

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Characteristics of Trace Metals by Instrumental Neutron Activation Analysis in Taejon Industrial Complex (기기 중성자 방사화 분석법을 이용한 대전공단지역의 대기중 미량 금속의 특성)

  • 구부미;임종명;장미숙;이진홍
    • Proceedings of the Korea Air Pollution Research Association Conference
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    • 2001.11a
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    • pp.123-124
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    • 2001
  • 본 연구는 대전 1, 2 공단지역을 대상으로 2000년 4월부터 2001년 1월까지 매주 1회, 24시간동안 분진시료를 포집하고, 포집된 42개의 시료를 대상으로 기기 중성자 방사화 분석법을 이용하여 독성 중금속을 포함한 약 30여종의 미량금속을 정량하고 그 특성을 파악하고자 한다. (중략)

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Characterization of Korean Clays and Pottery by Neutron Activation Analysis (III). A Classification Rule for Unknown Korean Ancient Potsherds

  • Lee, Chul;Kwun, Oh-Cheun;Jung, Dae-Il;Lee, Ihn-Chong;Kim, Nak-Bae
    • Bulletin of the Korean Chemical Society
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    • v.7 no.6
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    • pp.438-442
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    • 1986
  • A number of Korean potsherd samples has been classified by Fisher's discriminant method for the training set of Kyungki, Koryung and Kyungnam groups. The Koryung samples have been further classified for the training set of Koryung A, B and C subgroups. The training sets have been used to define classification of unknown samples and clay samples so as to find out some similarity between clay samples and certain potsherd groups.

A Comparative Study on Effective One-Group Cross-Sections of ORIGEN and FISPACT to Calculate Nuclide Inventory for Decommissioning Nuclear Power Plant

  • Cha, Gilyong;Kim, Soonyoung;Lee, Minhye;Kim, Minchul;Kim, Hyunmin
    • Journal of Radiation Protection and Research
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    • v.47 no.2
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    • pp.99-106
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    • 2022
  • Background: The radionuclide inventory calculation codes such as ORIGEN and FISPACT collapse neutron reaction libraries with energy spectra and generate an effective one-group cross-section. Since the nuclear cross-section data, energy group (g) structure, and other input details used by the two codes are different, there may be differences in each code's activation inventory calculation results. In this study, the calculation results of neutron-induced activation inventory using ORIGEN and FISPACT were compared and analyzed regarding radioactive waste classification and worker exposure during nuclear decommissioning. Materials and Methods: Two neutron spectra were used to obtain the comparison results: Watt fission spectrum and thermalized energy spectrum. The effective one-group cross-sections were generated for each type of energy group structure provided in ORIGEN and FISPACT. Then, the effective one-group cross-sections were analyzed by focusing on 59Ni, 63Ni, 94Nb, 60Co, 152Eu, and 154Eu, which are the main radionuclides of stainless steel, carbon steel, zircalloy, and concrete for decommissioning nuclear power plant (NPP). Results and Discussion: As a result of the analysis, 154Eu and 59Ni may be overestimated or underestimated depending on the code selection by up to 30%, because the cross-section library used for each code is different. When ORIGEN-44g, -49g, and -238g structures are selected, the differences of the calculation results of effective one-group cross-section according to group structure selection were less than 1% for the six nuclides applied in this study, and when FISPACT-69g, -172g, and -315g were applied, the difference was less than 1%, too. Conclusion: ORIGEN and FISPACT codes can be applied to activation calculations with their own built-in energy group structures for decommissioning NPP. Since the differences in calculation results may occur depending on the selection of codes and energy group structures, it is appropriate to properly select the energy group structure according to the accuracy required in the calculation and the characteristics of the problem.

Determination of Uranium in Groundwater by Instrumental Neutron Activation Analysis (중성자방사화분석에 의한 지하수중 우라늄의 정량)

  • 정용삼;문종화;정영주;박광원
    • Journal of the Korean Society of Groundwater Environment
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    • v.5 no.4
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    • pp.210-214
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    • 1998
  • In general the concentration of uranium in natural water such as fresh water and sea water is in the range of 0.01∼5 ppb, therefore trace analytical technique is required. The aim of present work is to compare a direct and preconcentration methods by evaporation and to investigate rapid and accurate trace analysis of uranium in groundwater using Instrumental Neutron Activation Analysis (INAA) which are sensitive and nondestructive method. Identification of analytical procedure was carried out using uranium standard solution of the range of 0.5∼100 ppb. In the given concentration, the deviation of calibration curve was less than 2%, and the standard deviation of measured values at each concentration was the range of 2∼12%. The difference of U content with sampling time for the same sample site was about 10.3%. Using this established method, the concentrations of uranium in samples collected at the 17 spring of Choongchung areas were found to be in the range of 1∼80 ppb.

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