• 한국수소및신에너지학회논문집
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• 제24권4호
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• pp.295-301
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• 2013

Long-term global energy-demand growth is expected to increase driven by strong energy-demand growth from developing countries. Fusion power offers the prospect of an almost inexhaustible source of energy for future generations, even though it also presents so far insurmountable scientific and engineering challenges. One of the challenges is safe handling of hydrogen isotopes. Metal hydrides such as depleted uranium hydride or ZrCo hydride are used as a storage medium for hydrogen isotopes reversibly. The metal hydrides bind with hydrogen very strongly. In this paper, we carried out a modeling and simulation work for absorption/desorption of hydrogen by ZrCo in a horizontal annulus cylinder bed. A comprehensive mathematical description of a metal hydride hydrogen storage vessel was developed. This model was calibrated against experimental data obtained from our experimental system containing ZrCo metal hydride. The model was capable of predicting the performance of the bed for not only both the storage and delivery processes but also heat transfer operations. This model should thus be very useful for the design and development of the next generation of metal hydride hydrogen isotope storage systems.

• 분석과학
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• 제16권2호
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• pp.117-124
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• 2003

고온 건식공정의 사용후핵연료 산화분말 ($U_3O_8$)과 경 중수로 연계 핵연료 제조공정의 $UO_2$ 소결체 물성 이해에 필요한 Oxygen/Metal 비를 습식 및 건식 분석방법으로 측정하였다. $UO_2$ 분말에 핵분열생성물 원소의 산화물을 일정량 첨가하고 $1,700^{\circ}C$의 수소분위기에서 소결시켜 20,000~60,000 MWd/MtU 연소도 범위의 사용후핵연료와 화학조성이 유사한 모의 사용후핵연료를 제조하였다. 습식법에 의한 O/M 비 측정을 위하여 혼합산 (10 M HCl : 8 M $HNO_3$, 2.5:1 V/V)에 의한 가압산분해법으로 모의 사용후핵연료를 용해하고 우라늄과 핵분열생성물 원소를 추출 크로마토그래피로 분리한 후 금속원소의 총량을 유도결합플라스마 원자방출분광분석법으로 결정하였다. 또한 $UO_2$가 산화될 때의 무게변화를 열중량 무게분석법 (thermogravimetric)으로 측정하여 O/M비를 계산하고 습식법으로 얻은 결과와 비교하였다. $Mo_{0.4}-Ru_{0.4}-Rh_{0.1}-Pd_{0.1}$ 합금이 O/M비 측정에 미치는 영향을 조사하였다.

• 한국소성가공학회:학술대회논문집
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• 한국소성가공학회 2003년도 춘계학술대회논문집
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• pp.303-306
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• 2003

To reduce the storage space of spent fuels used at the atomic power plants all over the world, the uranium elements contained in the spent fuels is being extracted and effectively stored. For this, the spent fuel are oxidized and deoxidized. In this study, it is produced conceptual design specification about the spent fuel management technology research and test facilities have been produced. The first considered processes in the facilities is the metal conversion furnace in the dry environment. Since this process is operates at the high temperature range, we have to consider heat-resisting designs for the device. For the heat-resisting designs, we have surveyed and analyzed technical references for material properties. Also, we have determined the temperature distribution condition of the device based on experimental results. We have calculated thermal stress and strain of each devices by the commercial analysis software, I-DEAS. By using the results, we have analyzed design configurations of the point at issue by thermal effects, and suggested alternative design configurations. It is experimented for inspecting confidence rate of heat strain. Based on these results, necessary design specifications for heat-resisting design have been produced.

• Nuclear Engineering and Technology
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• 제42권2호
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• pp.183-192
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• 2010

An electrochemical reduction of a mixture of metal oxides was conducted in a LiCl molten salt containing 3 wt% $Li_2O$ at $650^{\circ}C$. The oxide reduction was carried out by applying a current to an electrolysis cell, and the $Li_2O$ concentration was analyzed during each run. The concentration of $Li_2O$ in the electrolyte bulk phase gradually decreases according to Faraday's law due to a slow diffusion of the $O^{2-}$ ions. A hindrance effect of the unreduced metal oxides was observed for the reduction of the uranium oxide. Cs, Sr, and Ba of high heat-load fission products were diffused into and accumulated in the salt phase as predicted with thermodynamic consideration.

• 환경위생공학
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• 제15권1호
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• pp.77-87
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• 2000

클로로메틸화된 스틸렌, 1,4-디비닐벤젠과 동공의 크기를 달리한 여러 가지 거대고리 화합물을 개시제로 하여 공중합법에 의하여 1%, 2%, 10% 및 20%의 가교도를 가진 새로운 이온 교환수지를 합성하였다. 그리고 이들 수지에 대한 우라늄(VI), 니켈(II) 및 네오듐(III) 금속에 대한 흡착특성을 검토하였다. 이 수지들은 강산, 강염기 및 열에 대해서 안정하였으며, pH 4.0 이상에서는 $UO_2^{2+}$ 이온에 대한 겉보기용량이 가장 크게 나타났고, 합성수지들은 네오듐(III) 금속이온에 대하여 선택성을 보였다.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.2792-2800
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• 2022

In the core of the WWR-K reactor, a long-term irradiation of tristructural isotopic (TRISO)-coated fuel particles (CFPs) with a UO₂ kernel was carried out under high-temperature gas-cooled reactor (HTGR)-like operating conditions. The temperature of this TRISO fuel during irradiation varied in the range of 950-1100 ℃. A fission per initial metal atom (FIMA) of uranium burnup of 9.9% was reached. The release of gaseous fission products was measured in-pile. The release-to-birth ratio (R/B) for the fission product isotopes was calculated. Aspects of fuel safety while achieving deep fuel burnup are important and relevant, including maintaining the integrity of the fuel coatings. The main mechanisms of fuel failure are kernel migration, silicon carbide corrosion by palladium, and gas pressure increase inside the CFP. The formation of gaseous fission products and carbon monoxide leads to an increase in the internal pressure in the CFP, which is a dominant failure mechanism of the coatings under this level of burnup. Irradiated fuel compacts were subjected to electric dissociation to isolate the CFPs from the fuel compacts. In addition, nondestructive methods, such as X-ray radiography and gamma spectrometry, were used. The predicted R/B ratio was evaluated using the fission gas release model developed in the high-temperature test reactor (HTTR) project. In the model, both the through-coatings of failed CFPs and as-fabricated uranium contamination were assumed to be sources of the fission gas. The obtained R/B ratio for gaseous fission products allows the finalization and validation of the model for the release of fission products from the CFPs and fuel compacts. The success of the integrity of TRISO fuel irradiated at approximately 9.9% FIMA was demonstrated. A low fuel failure fraction and R/B ratios indicated good performance and reliability of the studied TRISO fuel.

• 화약ㆍ발파
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• 제19권1호
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• pp.101-110
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• 2001

Depleted uranium (DU) outperforms tungsten heavy alloys (WHA) by about 10%. Because of environmental and hence, political concerns, there is a need to improve WHA performance, in order to replace the DU penetrators. A technique of metal powder compaction by the detonation of an explosive has been applied to tungsten-titanium(W-Ti) powder materials that otherwise may be difficult to fabricate conventionally or have dissimilar, nonequilibrium, or unique me1astab1e substructures. However, the engineering properties of compacted materials are not widely reported and are little known especially for the "unique" composition of W-Ti alloy. To develop high-performance tungsten composites with superior ballistic attributes, it is necessary to understand, carefully document controlled experimental results, and develop basic computational models for potential composites with controlled microstructures. A detailed understanding and engineering application of W-Ti alloy can lead to the development of new structural design for engineering components and materials.

• 자원환경지질
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• 제31권5호
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• pp.365-374
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• 1998

Economic U- and Th-bearing pegmatite deposits occur in the Kyemyeongsan Formation, and are spatially closely associated with the Carboniferous alkali granite. The pegmatite is lithochemically alkaline and peralumious, and consists mainly of potassic feldspar and quartz with allanite and U- and Th-bearing minerals. Paragenetic stages of mineralization in the pegmatite are divided as follows: early silicate mineralization, main rare metal mineralization, and late silicate mineralization. Thorite, euxenite, fergusonite and uranpyrochlore are the predominant U- and Th-bearing minerals. Both the enrichments of Nb, Y, Th, U, and Ta and the depletions of Hf, Ba, and Rb in the pegmatite were resulted from magmatic differentiation. The increases of Na and Ca in uranpyrochlore, of Th and U in fergusonite, of Si, Th, U and Pb in thorite, and of Nb and Y in euxenite were possibly resulted from both later internal fractionation and hydrothermal alteration. The variation of chemical composition in a mineral species reflects the different pysico-chemical conditions during the crystallization.

• Bulletin of the Korean Chemical Society
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• 제21권12호
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• pp.1187-1192
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• 2000

Ternary (Mo-Ru-Pd) and binary (Mo-Ru, Mo-Pd) alloys have been prepared using an Ar arc melting furnace. Mo and the noble metals, Ru and Pd, are the constituents of metallic insoluble residues, which were found in the early days of post-irradiation studies on uranium oxide fuels. In the present study, the structure of the alloys was evaluated using a powder X-ray diffractometer. Unit cell parameters were determined by least squares refinements of powder X-ray diffraction data. Scanning electron microscopic analyses of the surface of the alloys indicated that surface morphology was dependent on the crystallographic structure as well as its composition. Measurements of the magnetic susceptibility of the alloys showed evidence of superconducting transition from 3 to 9.2 K. Among the ternary and binary alloys, the ${\sigma}-phase$ showed the highest superconducting transition temperature,~9.2 K.

• 분석과학
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• 제23권1호
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• pp.45-53
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• 2010

우라늄 화합물 중에 함유된 염소를 정량하기 위하여 수증기증류 및 열가수분해를 이용한 량 염소의 분리 및 정량법을 개발하였다. 수증기 증류에 의한 시료 중의 염소를 분리하기 위하여 수증기 발생장치, 증류플라스크 및 냉각기 등으로 구성된 장치를 제작 설치하였다. LiCl 표준용액과 모의사용후핵 연료 일정량을 혼합하여 만든 우라늄 화합물 시료 중의 염소를 분리하기 위하여 혼산(0.2 M ferrous ammonium sulfate-0.5M sulfamic acid 3 mL + phosphoric acid 6 mL + sulfuric acid 15 mL)을 이용하여 $140^{\circ}C$로 증류시키고 $90{\pm}5\;mL$를 수집하였다. 열가수분해에 의한 시료 중의 염소를 분리하기 위하여 공기공급장치, 온수공급장치, 석영반응관, 연소로 및 연소보트, 그리고 휘발 염소 흡수장치로 구성된 열가수분해장치를 제작 설치하였다. 일정량의 우라늄 화합물 시료에 반응촉진제($U_3O_8$)를 가하고 1 mL/min의 공기유속과 $80^{\circ}C$의 공급수 온도를 유지하고 $950^{\circ}C$에서 1시간 반응시켜 시료 중의 염소를 분리하였다. 두 방법에 의하여 수집된 각 흡수용액은 일정부피로 희석하고 이온크로마토그래피로 정량하여 회수율을 측정하였다. 금속전환체 잔류 용융염 중의 미량 염소를 이온크로마토그래피로 정량하기 위하여 시료를 공기 및 건조 산화시키고 분쇄한 후 열가수분해하여 염소를 회수하였다.