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EPMA를 이용한 DUPIC 사용후 핵연료 핵분열 생성물의 특성 분석
정양홍,유병옥,주용선,이종원,정인하,김명한 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.2
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.
A Study on the Crystalline Boron Analysis in CRUD in Spent Fuel Cladding Using EPMA X-ray Images
정양홍,백승제,진영관 한국부식방식학회 2020 Corrosion Science and Technology Vol.19 No.1
Chalk River Unidentified Deposits (CRUDs) were collected from the Korean pressurized water reactor (PWR)plant (A, B, and C) where the axial offset anomaly (AOA) occurred. AOA, also known as a CRUD-inducedpower shift, is one of the key issues in maintaining stable PWR plant operations. CRUDs were sampledfrom spent nuclear fuel rods and analyzed using an electron probe micro-analyzer (EPMA). This paper describesthe characteristics of boron-deposits from the CRUDs sampled from twice-burnt assemblies from the KoreanPWR. The primary coolant of a PWR contains boron and lithium. It is known that boron deposition occursin a thick CRUD layer under substantial sub-cooled nucleate boiling (SNB). The results of this study aresummarized as follows. Boron was not found at the locations where the existence was confirmed in simulatedCRUDs, in other words, the cladding and CRUD boundaries. Nevertheless, we clearly observed the presenceof boron and confirmed that boron existed as a lump in crystalline form. In addition, the study confirmedthat CRUD existed in a crystal form with a unique size of about 10 μm.
정양홍,주용선 한국부식방식학회 2020 Corrosion Science and Technology Vol.19 No.5
Radioactive corrosion product specimens were analyzed using an electron probe microanalyzer (EPMA) andX-ray image mapping. It is difficult to analyze the composition of radioactive corrosion products usingan EPMA due to the size and rough shape of the surfaces. It is particularly challenging to analyze thecomposition of radioactive corrosion products in the form of piled up, small grains. However, useful resultscan be derived by applying a semi-quantitative analysis method using an EPMA with X-ray images. Astandard-less, semi-quantitative method for wavelength dispersive spectrometry. EPMA analysis was developedwith the objective of simplifying the analytical procedure required. In this study, we verified the reasonabletheory of semi-quantitative analysis and observed the semi-quantitative results using a sample with a goodsurface condition. Based on the validated results, we analyzed highly rough-surface radioactive corrosionproducts and assessed their composition. Finally, the usefulness of the semi-quantitative analysis was reviewedby verifying the results of the analysis of radioactive corrosion products collected from spent nuclear fuelrods.
EPMA를 이용한 사용후핵연료의 연소도 측정에 관한 연구
정양홍,유병옥,오완호,이홍기,주용선,홍권표,Jung, Yang-Hong,Yoo, Byung-Ok,Oh, Wan-Ho,Lee, Hong-Gy,Choo, Yong-Sun,Hong, Kwon-Pyo 한국현미경학회 2005 Applied microscopy Vol.35 No.3
차폐형 성분분석기 (Shielded EPMA)를 이용하여 한국형 경수로발전소에서 연소된 35,000 MWd/MTU, U-235의 농축도 3.2%인 $UO_2$ 사용후핵연료의 연소도 측정 방법을 제시하였다. 원자로의 출력과 핵연료의 특성 및 중성자속 분포 등 중요한 핵공학적 정보를 제공하는 사용후핵연료의 연소도는 U-235의 감손에 따른 무거운 핵종의 변화를 측정하거나 사용후핵연료 내에 생성된 핵분열 생성물을 측정하는 방법 등이 있다. 이러한 방법은 비파괴시험으로도 하고 있으나 파괴시험인 화학적 분석방법이 보다 정확한 것으로 인식되고 있다. 그러나 화학분석법은 분석시간이 많이 걸리며, 방사선 시료의 취급으로 인한 시험자의 피폭 등의 어려움이 따른다. 화학적 분석방법에 의한 연소도 측정방법 대신 분석시료의 제작 및 분석시간이 화학적 분석방법에 비해 상당히 짧고, 또한 국부적인 연소도 측정이 요구되는 사고 핵연료나 고연소 핵연료의 위치별 연소도 측정이 가능한 EPMA를 사용한 연소도 측정기술이 개발되고 있다. 시험결과 ORIGEN2 코드로 계산한 연소도에 따른 Nd의 농도와 EPMA 분석에 의한 Nd의 농도는 거의 일치하였다. EPMA로 분석한 Nd의 조성과 ORIGEN-2 코드로 계산한 Nd의 조성 분포를 이용하여 사용후핵연료의 연소도를 예측하는 일차 실험식을 유도하였으며, 그 결과가 화학분석에 의한 연소도와 거의 일치함을 확인하였다. 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.
Investigation of Pellet-Clad Mechanical Interaction in Failed Spent PWR Fuel
정양홍,백승제 한국부식방식학회 2019 Corrosion Science and Technology Vol.18 No.5
A failed spent fuel rod with 53,000 MWd/tU from a nuclear power plant was characterized, and the fissionproducts and oxygen layer in the pellet-clad mechanical interaction region were observed using an EPMA(Electron Probe Micro-Analyzer). A sound fuel rod burned under similar conditions was used to compareand analyze, the results of the failed fuel rod. In the failed fuel rod, the oxide layer represented 10 μmof the boundary of the cladding, and 35 μm of the region outside the cladding. By comparison, in thesound fuel rod, the oxide layer was 8 μm, observed in the cladding boundary region. The cladding innersurface corrosion and the resulting fuel-cladding bonding were investigated using an EPMA. Zirconiumexisted in the bonding layer of the (U, Zr)O compound beyond the pellet cladding interaction gap of 20μm, and composition of UZr2O3 was observed in the failed fuel rod. This paper presents the results ofthe EPMA examination of a spent fuel specimen, and a technique to analyze fission products in the pellet-cladmechanical interaction region.