• Proceedings of the Korea Air Pollution Research Association Conference
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• 1999.10a
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• pp.393-394
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• 1999

최근에 개발된 ultrathin window를 장착한 electron probe X-ray microanalysis(EPMA) 분석법(Ro et. el., 1999; Osan et. al., 1999; Szaloki et. al., 1999)은 종래의 통상적인 EPMA 방법으로는 분석하기 어려웠던 탄소, 질소, 산소 등의 원소를 정량적으로 분석할 수 있는 가능성을 제시하였다. 개개 입자의 형태와 크기 뿐 아니라 화학조성에 대한 정보를 제공하는 EPMA 분석법은 대기 중 개개 입자에 대한 생성, 이동, 반응 및 소멸에 관한 자세한 정보를 제공하기 때문에 지난 20여 년간 이 분석법을 사용하여 많은 연구가 진행되어 왔다.(중략)

• Corrosion Science and Technology
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• v.19 no.5
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• pp.231-238
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• 2020

Radioactive corrosion product specimens were analyzed using an electron probe microanalyzer (EPMA) and X-ray image mapping. It is difficult to analyze the composition of radioactive corrosion products using an EPMA due to the size and rough shape of the surfaces. It is particularly challenging to analyze the composition of radioactive corrosion products in the form of piled up, small grains. However, useful results can be derived by applying a semi-quantitative analysis method using an EPMA with X-ray images. A standard-less, semi-quantitative method for wavelength dispersive spectrometry. EPMA analysis was developed with the objective of simplifying the analytical procedure required. In this study, we verified the reasonable theory of semi-quantitative analysis and observed the semi-quantitative results using a sample with a good surface condition. Based on the validated results, we analyzed highly rough-surface radioactive corrosion products and assessed their composition. Finally, the usefulness of the semi-quantitative analysis was reviewed by verifying the results of the analysis of radioactive corrosion products collected from spent nuclear fuel rods.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.2
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• pp.125-133
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• 2004

Fission products of DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors) fuel, irradiated in HANARO research reactor with 61 ㎾/m of maximum linear power and 1,770 ㎿d/tU of average burn-up, was characterized by EPMA(Electron Probe Micro Analyzer). In order to find accurate characterization, the analysis results by EPMA of fresh simulated DUPIC fuel containing fission products as chemicals were compared with that of wet chemical analysis. The metallic precipitates observed at the center of the fresh simulated DUPIC fuel were about 1 $\mu\textrm{m}$ in size and their major components by EPMA were Mo-53.89 at.%, Ru-37.40 at.%, and Pd+Rh-8.71 at.%. Established procedure through the fresh simulated DUPIC fuel was applied to the irradiated DUPIC fuel. Observed size of metallic precipitates were 2∼2.5 $\mu\textrm{m}$ and their compositions were Mo-47.34 at.%, Ru-46 at.%, and Pd+Rh-6.65 at.%. What are uncommon things for this experiment, special treatment for improving the conductivity was attempted to the specimen and the conditions of exact irradiation of electron beam to small metallic precipitate were suggested.

• Analytical Science and Technology
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• v.17 no.4
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• pp.355-362
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• 2004

Fission products and Inter reaction layer of $U_3Si-Al$ dispersion fuel, irradiated in HANARO research reactor with 121 kW/m of maximum liner power and 63 at% of average burn-up, was characterization by EPMA (Electron Probe Micro Analyzer). The fuel punching system developed by Irradiated Materials Examination Facility (IMEF) has used to make these samples for the EPMA. With this system a very small and thin specimen which is 1.57 mm in diameter and 2 mm in thickness respectively has been fabricated to protect the EPMA operator from high radioactive fuel and to mini-mize the equivalent dose rate less than 150 mSv/h. EPMA was performed to observe layers of sectional, Inter-reaction and oxide with specimens of cutting and polished. Stoichiometry in the Inter-reaction layer with $16{\mu}m$ of thickness was $U_{2.84}$ Si $Al_{14}$ with calibration of $UO_2$ and $U_{3.24}$ Si $Al_{14.1}$ with calibration of standard specimen. metallic precipitates in this layer were not observed using fission products examination.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.15 no.5
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• pp.3292-3297
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• 2014

The vehicle wiper blade(W/B) to lower the friction coefficient of the rubber surface after the surface treatment with chlorine were investigated. IR spectrum from W/B was used to determine the extent of chlorination of the rubber surface. Coefficient of friction is significantly reduced by the treatment with chlorine. In particular, the more sensitive influence on the initial chlorination. Rubber surface properties with respect to the longitudinal direction of the cutting plane were obtained by EPMA line analysis results. Penetration depth by EPMA chlorine concentration($20.0{\ell}$ of water for 35.0% hydrochloric acid(HCl) $300m{\ell}$ with 5.25% sodium hypochlorite(NaOCl) $400m{\ell}$), the chlorine treatment for 5 minutes was conducted to find that after 1.2 ${\mu}m$.

• Corrosion Science and Technology
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• v.17 no.6
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• pp.265-271
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• 2018

CRUD specimens, scraped from twice-burned fuel cladding in the Korean Nuclear Power Plant, were analyzed using Shielded-EPMA. The principal elements of the CRUD were identified as Ni and Fe, at an approximate ratio of 1.3 Ni/Fe. To investigate the morphology and composition of the pure metallic materials in the CRUD, coolant impurities must be removed. This can be accomplished by increasing the EPMA current to an abnormally high intensity until the impurities are melted. Normally, EPMA applications are performed at conditions of 20 kV voltage and 20 nA current. But in our study, the applied current was increased up to 1200 nA, over time increments ranging from 5 to 30 seconds. This technique was performed by opening an adjustable aperture for the gun alignment. Results showed impurities contained in the CRUD material disappeared and pure metal materials, e.g., Ni and Fe, remained. This method presents an innovative way to analyze CRUD.

• Journal of Periodontal and Implant Science
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• v.38 no.3
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• pp.503-510
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• 2008

Purpose: To evaluate bone formation on the implant surface between machined fixture and RBM surface fixture through analyzing of distribution and concentration of Ca and P by EPMA. Material and Methods: Fixtures had divided in 2 group: Machined(Group I), RBM (Group II). Total 4 fixtures were implanted on rabbit which sacrificed on 2 week and 4 week for the histological specimens. By these specimens EPMA value were measured, compared and analysed by each group to figure out the evidence of clinical use of RBM implant. Result: After 2 weeks and 4 weeks, it was analyzed that bone formation area, distribution and concentration of Ca and P by EPMA. In distribution and concentration of P Group II was higher than Group I, but there were no statistical significances. In new bone formation area, Group II was more higher than Group I with statistically significances. Both of group, after 4 weeks area is little bit higher than after 2 weeks area but there is no statistically significances. Conclusion: RBM implant was better than machined implant on the early bone formation.

• Corrosion Science and Technology
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• v.20 no.3
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• pp.118-128
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• 2021

The oxide layer in samples taken from an irradiated Zr-2.5Nb pressure tube from a CANDU-PHWR reactor was analyzed using electron probe microanalysis (EPMA). The examined tube had been exposed to temperatures ranging from 264 to 306 ℃ and a neutron fluence of 8.9 × 10²¹ n/cm² (E > 1 MeV) for the maximum 10 effective full-power years in a nuclear power plant. Measuring oxide layer thickness generally employs optical microscopy. However, in this study, analysis of the oxide layer from the irradiated pressure tube components was undertaken through X-ray image mapping obtained using EPMA. The oxide layer characteristics were analyzed by X-ray image mapping with 256 × 256 pixels using EPMA. In addition, the slope of the oxide layer was measured for each location. A particular advantage of this study was that backscattered electrons and X-ray image mapping were obtained at a magnification of 9,000 when 20 kV volts and 30 uA of current were applied to radiation-shielded EPMA. The results of this study should usefully contribute to the study of the oxide layer properties of various types of metallic materials irradiated by high radiation in nuclear power plants.

• Applied Microscopy
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• v.35 no.3
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• pp.113-119
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• 2005

The Methodology of burnup calculation with EPMA test set up in this study. The spent fuel from PWR nuclear power plant was used as specimen. This $UO_2$ fuel with 3.2% of enrichment had been irradiated up to 35,000 MWd/MTU. The burnup is very important factor for nuclear fuel to estimate all fuel behaviors in reactor. To measure amounts of fission products and actinides for the burnup calcualation, destructive method analysis has been used but it makes long experimental time and second radio-wastes. In this study, EPMA test was available to measure amount of fission products. Neodymium is able to be detected and quantified. It can be compared with the results from chemical analysis and ORIGEN-2 code calculation. Concentration of Nd from EPMA test showed good agreement with result of ORIGEN-2 code in the same burnup.

• Proceedings of the Materials Research Society of Korea Conference
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• 1999.11a
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• pp.39-39
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• 1999