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400-700 $^{\circ}C$의 온도범위에서 모의 핵연료의 산화거동
강권호 한국분말야금학회 1999 한국분말재료학회지 (KPMI) Vol.6 No.3
The oxidation behavior of the simulated spent fuel of burn up 33 MWD/kgU was investigated to predict that of the spent fuel in the temperature ranges of 400 to $700^{\circ}C$ and was compared with those of $UO_2$. The forms of uranium oxides after the oxidation were conformed by XRD analyses. The oxidation rate at each the temperature and the activation energy were obtained. After complete oxidation, the simulated spent fuel was converted to $U_3O_8$ and pulverized to powder due to the density difference between the simulated spent fuel and uranium oxides. The activation energies were 85.35 and 30.77kJ/mol in the temperature ranges of 400$\leq$T($^{\circ}C$)$\leq$500 and 500$\leq$T($^{\circ}C$)$\leq$700, respectively.
강권호,배기광,박희성,송기찬,문제선 한국분말야금학회 2000 한국분말재료학회지 (KPMI) Vol.7 No.3
The simulated DUPIC fuel provides a convenient way to investigate fuel properties and behaviours such as thermal conductivity, thermal expansion, fission gas release, leaching and so on. Several pellets simulating the composition and microstructure of the DUPIC fuel were fabricated from resintering powder through the OREOX process of the simulated spent fuel pellets, which were prepared from the mixture of stable forms of constituent nuclides. This study describes the powder treatment, OREOX, compaction and sintering to fabricate simulated DUPIC fuel using the simulated spent fuel. The homogeneity of additives in the powder was observed after attrition milling. The microstructure of the simulated spent fuel was in agreement with the previous studies. The densities and the grain size of simulated DUPIC fuel was pellets are higher than those of simulated spent fuel pellets. Small metallic precipitates and oxide precipitates were observed on matrix grain boundaries.
강권호,류호진,배정현,송기찬,양명승 한국에너지학회 2001 에너지공학 Vol.10 No.3
본 연구에서는 경수로 사용후핵연료를 모사하는 모의 핵연료 제조 공정 중 소결체 특성에 미치는 변수들의 영향에 관하여 기술하였다. 주로 성형압, 소결 온도 및 시간이 소결체의 밀도에 미치는 영향에 관하여 분석하였다. 성형압은 1 ton/$\textrm{cm}^2$에서 4ton/$\textrm{cm}^2$, 소결 온도는 167$0^{\circ}C$, 173$0^{\circ}C$, 178$0^{\circ}C$, 소결 시간은 4시간, 8시간, 24시간으로 변화시키면서 실험을 수행하였다. 성형밀도는 성형압의 1/3승에 비례하며, 이론 밀도의 약 90.5%에서 99.6%까지의 소결 밀도를 갖는 모의 핵연료를 제조하였다. 결정립 성장지수와 활성화에너지는 각각 2.5와 287.97kJ/mo1 이었다. In this study, the effects of the variables on sintering of simulated fuel to simulate the spent fuel are described. Mainly, the effects of compaction pressure, sintering temperature and time on the density of pellet are described. The experimental is performed with compaction pressure of 1 ton/$\textrm{cm}^2$~4 ton/$\textrm{cm}^2$, sintering temperature of 167$0^{\circ}C$, 173$0^{\circ}C$ and 178$0^{\circ}C$ and sintering time of 4 hr, 8 hr and 24 hr. The green density of simulated fuel is proportional to the one third power of compaction pressure and the sintered density is 90.5~99.6% of theoretical density. The grain growth exponent and activation energy of simulated fuel is 2.5 and 287.97 kJ/mol, respectively.
강권호,나상호,문흥수,오세용 한국에너지학회 2006 에너지공학 Vol.15 No.1
- The oxidation behavior of UO2 pellet was studied using an XRD and a thermogravimetric analyzer in the temperature range from 573 to 873 K and in the density range from 94.64 to 99.10% of theoretical density in air. It was found from the XRD study that UO2 was completely converted to U3O8 in this experimental temperature range. The formation of U3O8 displays sigmoidal reaction kinetics. The oxidation rate was reduced with density. Induction time for the oxidation of UO2 was delayed with density because of open pore formed in surface of UO2 pellet. The activation energy for oxidation of UO2 was determined to be 89.54 kJ/mol and 34.40 kJ/mol in the temperature range from 573 to 723 K and from 723 to 873 K, respectively.