• 대한화학회지
• /
• 제27권5호
• /
• pp.361-367
• /
• 1983

이온 교환수지에 의한 국산모나자이트 중에 함유된 우라늄을 분리, 회수하기 위하여 강염기성 이온교환수지(Amberlite IRA-900)에 S$O_4^{2-}$ 및 P$O_4^{3-}$ 이온을 흡착시켜 황산우라닐착이온, 인산우라닐착이온 형태로 우라늄을 흡착시켜 적당한 용리액(HN$O_3$ : N$NH_4NO_3$)으로 우라늄을 분리 회수하는 실험을 하였다. 표준우라늄을 사용하였을 때 황산형수지에서 99.3%, 인산형수지에서 99.2%까지 회수하였으며 모자나이트를 황산분해한 모나자이트 황산분해용액 중의 희토류원소들을 제거한 용액을 사용하였을 때는 약 92%까지 회수하였다. 모나자이트 중에 함유된 인산이온의 방해가 없는 것으로 나타났다. 인산형수지에서 우라늄의 회수율이 51% 정도인 것으로 보아 모나자이트를 황산으로 분해하였을 때는 대부분의 우라늄은 황산우라닐착이온으로 된다는 사실도 확인하였다.

• 한국정밀공학회:학술대회논문집
• /
• 한국정밀공학회 2009년도 춘계학술대회 논문집
• /
• pp.693-694
• /
• 2009

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 2005년도 춘계학술발표회
• /
• pp.373-374
• /
• 2005

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2012년도 추계학술논문요약집
• /
• pp.69-70
• /
• 2012

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2016년도 춘계학술논문요약집
• /
• pp.83-84
• /
• 2016

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2017년도 추계학술논문요약집
• /
• pp.75-76
• /
• 2017

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2011년도 추계학술논문요약집
• /
• pp.163-164
• /
• 2011

• 설비공학논문집
• /
• 제13권8호
• /
• pp.796-802
• /
• 2001

The purpose of the present study is to examine the heat transfer characteristics of the U-shape heat pipe for the cooling of semiconductor in subway train. Perflouro-carbon(PFC) was used as working fluid. Temperature distribution on the surface and heat transfer coefficients were investigated according to the working fluid volume percent and heating rate. The results were as follows; Optimum volumetric percent of working fluid was from 80% to 90%, and hat transfer coefficients of evaporation and condensation were as follows, respectively. $\hbar_ie=0.37\times(\frac{P_i}{P_O})$l_c}^0.3$,$\hbar_ic-4.2(\frac{\kappa_l^3p_l^2gh_fg}{\mu_lq_c_l_c}^\frac{1}{3}

• 한국분말재료학회지
• /
• 제16권2호
• /
• pp.115-121
• /
• 2009

The effects of thermal treatment conditions on ADU (ammonium diuranate) prepared by SOL-GEL method, so-called GSP (Gel supported precipitation) process, were investigated for $UO_2$ kernel preparation. In this study, ADU compound particles were calcined to $UO_3$ particles in air and Ar atmospheres, and these $UO_3$ particles were reduced and sintered in 4%-$H_2$/Ar. During the thermal calcining treatment in air, ADU compound was slightly decomposed, and then converted to $UO_3$ phases at $500^{\circ}C$. At $600^{\circ}C$, the $U_3O_8$ phase appeared together with $UO_3$. After sintering of theses particles, the uranium oxide phases were reduced to a stoichiometric $UO_2$. As a result of the calcining treatment in Ar, more reduced-form of uranium oxide was observed than that treated in air atmosphere by XRD analysis. The final phases of these particles were estimated as a mixture of $U_3O_7$ and $U_4O_9$.

• Bulletin of the Korean Chemical Society
• /
• 제21권8호
• /
• pp.797-800
• /
• 2000

The reaction of o-acylthiophenacyl chloride 5a with onc equivalent ofsodium azide in aqueous acetone at-10~ $-5^{\circ}C$ gave 2,9-dimethyl-6H,I3H-dibenzo[d,i][1,6]dithiecin-7,14-dione 7(10%),acyclic dimer 8(64%),and tri-mer 9 (8%). Dimer 8 and trimer 9 we re converted readily to 7 under the similar conditions at room temperature in yields of 72% and 53%,respectivel. Also, one pot synthesis of 7 (64%, 45%) from the reaction of 5a or 5b with two equivalents of sodium azide at room temperature was very successful.