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질산용액에 UO<sub>2</sub> Pellet의 용해특성에 관한 연구
정원명,박진호,이규일,유재형,정경채,Choung, Won-Myung,Park, Jin-Ho,Lee, Kue-Il,Yoo, Jae-Hyung,Jeong, Kyung-Chai 한국공업화학회 1998 공업화학 Vol.9 No.3
의료용 동위원소인 fission Mo($^{99}Mo$)를 제조하기 위한 공정중 $UO_2$ 표적의 질산용해공정의 조업조건을 확립하기 위하여 $UO_2$ pellet의 유효표면적($s:0.034{\sim}0.282cm^2/g-UO_2$), 질산농도(1.5~10N), 반응온도 ($40{\sim}105^{\circ}C$)에 따른 $HNO_3$ pellet의 용해특성을 확인하였다. 그 결과 용해속도가 $UO_2$ pellet의 유효표면적에 정비례하며 표면적이 클수록 그 경향이 뚜렸함을 확인하였고, 반응속도와의 관계가 dc/dt = 10.6s로 나타났다. 용해속도와 질산농도와의 관계는 일정온도($90^{\circ}C$)에서 [$HNO_3$]1.42에 비례하는 것으로 나타났고, 온도변화에 따른 관계는 $90^{\circ}C$까지는 온도가 증가함에 따라 용해속도가 급격히 증가하나 그 이상에서는 오히려 감소하는 것으로 나타났으며, 활성화 에너지가 36.3KJ/mol로 계산되었다. The effects of surface area of $UO_2$ pellets($s:0.034{\sim}0.282cm^2/g-UO_2$), concentration of nitric acid(1.5~10N) and temperature($40{\sim}105^{\circ}C$) on the dissolution rate were investigated in this experiment. The results showed that dissolution rate of $UO_2$ pellets was in direct proportion to effective surface area(s) and well fit to linear plot in high surface area. The dissolution rate was expressed as dc/dt = 10.6s at $90^{\circ}C$, [$HNO_3$]=8N, and proportioned to the power 1.42 of $HNO_3$ concentration. And also, the results showed that dissolution rate was sharply increased according to temperature increase in temperature below $90^{\circ}C$, but decreased in temperature above $90^{\circ}C$. Activation energy(E) was evaluated to be 36.3KJ/mol.
선진 원자력발전국의 사용후핵연료 처리기술 및 정책현황과 우리나라의 관련연구 현황
유길성,정원명,구정회,조일제,국동학,권기찬,이원경,이은표,홍동희,유지섭,박성원,You, Gil-Sung,Choung, Won-Myung,Ku, Jeong-Hoe,Cho, Il-Je,Kook, Dong-Hak,Kwon, Kie-Chan,Lee, Won-Kyung,Lee, Eun-Pyo,Hong, Dong-Hee,Yoon, Ji-Sup,Park, Seong-W 한국방사성폐기물학회 2007 방사성폐기물학회지 Vol.5 No.4
Status on the spent nuclear fuel management policy and R&D plan of the major countries is surveyed. Also the prospect of the future R&D plan is suggested. Recently so-called fuel cycle nations, which have the reprocess policy of the spent fuel, announced new spent fuel management policy based on the advanced fuel cycle technology. The policy is focused to transmute highly radioactive material and material having a very long half-life, and to recycle the Pu and U contained in the spent fuel. In this way the radio-foxily of the spent fuel as well as the amount of the high level waste to be eventually disposed can greatly be reduced. Most of countries selected the wet process as a primary option for the treatment of the spent fuel since the advanced wet process, which is based on the existing PUREX process, looks more feasible as compared with the dry process. The wet process, however, is much more sensitive in terms of proliferation-resistance compared with the dry process. The pure Pu can easily be obtained by simply modifying the process. On the other hand the pure Pu can not be extracted in the dry process based on the high temperature molten salt process such as a pyroprocess. Even though the pyroprocess technology is very premature, it has a great merit. Thus it is necessary for Korea to have a long term strategy for pursuing a spent fuel treatment technology with a proliferation resistance and a great merit for the GEN-IV fuel cycles. Pyroprocess is one of the best candidates to satisfy these purposes.
사용후핵연료 처리를 위한 ACP 실증시설내 개폐형 작업대의 구조적 안전성 평가
권기찬,구정회,이은표,정원명,유길성,이원경,조일제,국동학,Kwon, Kie-Chan,Ku, Jeong-Hoe,Lee, Eun-Pyo,Choung, Won-Myung,You, Gil-Sung,Lee, Won-Kyung,Cho, Il-Je,Kuk, Dong-Hak 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.1
A demonstration facility for advanced spent fuel conditioning process (ACP) is under construction in KAERI. In this hot cell facility, all process equipments and materials are taken in and out only through the rear door. The working table in front of the process rear door is specially designed to be openable for the efficient use of the space. This paper presents the structural safety analysis of the openable working table, for the normal operational load condition and accidential drop condition of heavy object. Both cases are investigated through static and dynamic finite element analyses. The analysis results show that structural safety of the working table is sufficiently assured and the working table is not collapsed even when an object of 500 kg is dropped from the height of 50 cm.
사용후핵연료 차세대관리 종합공정 실증시설내 후면 차폐문의 구조적 안전성 평가
권기찬,구정회,이은표,정원명,유길성,이원경,국동학,조일제,Kwon, Kie-Chan,Ku, Jeong-Hoe,Lee, Eun-Pyo,Choung, Won-Myung,You, Gil-Sung,Lee, Won-Kyung,Kuk, Dong-Hak,Cho, Il-Je 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.1
A demonstration facility for an advanced spent fuel conditioning process (ACP) is under construction at KAERI. In this hotcell facility, the rear door is frequently used since all process equipment and materials are taken in and out only through the rear door. Therefore , both the structural safety and stability of the door are essentially required for the safety of ACP facility. In this paper, the finite element analysis has been performed to investigate the structural safety under the impact condition between the rear door and the door frame. Also the possibility of the rear door being tumbled over by the impact force or the inertia force under a sudden stop conditon has been evaluated. The analysis results demonstrate that the structural safety and stability of the rear door are sufficiently assured for both the impact and the accidential stop conditions.
김연구,정원명,박경배,박진호,황두성,이규일 한국공업화학회 2000 응용화학 Vol.4 No.1
Dissolution of the irradiated UO₂ target is the first step in process for separation and purification of fission ^(99)Mo, the only parent nuclide of ^(99m)Tc an extremely useful tool for medical diagnosis. In this study, the effects of concentration of sulfuric acid (0.5∼2N) and nitric acid(0.01∼0.1N), temperature on UO₂ pellets dissolution rate were investigated. The results of experiments showed that dissolution rate proportioned to the power 2.597 of H₂SO₄ concentration and 1.241 of HNO₃ concentration, and activation energy was evaluated to be 105.2 kJ/㏖. And also, the optimum operating condition for UO₂ target dissolution was suggested.