• 방사성폐기물학회지
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• 제7권3호
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• pp.161-165
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• 2009

핵연료 운반용 실린더의 재사용을 위한 용기세척공장의 제염공정에 대한 성능을 평가하기 위하여 ${Na_2}{CO_3}\;+\;{H_2}{O_2}$ 혼합용액의 조합을 약간 달리한 2회의 시험을 실행하였다. 각 시험은 모두 일련의 5 단계에 걸쳐 실시되었다. 우라늄 제염의 주 화학종은 ${Na_4}{UO_2}(CO_3)_3$로 식별되었다. 그리고 첫 단계에서의 세척 액은 물이었으며, 이 단계에서 50% 이상의 우라늄이 제염되었다. 그 이후로는 단계가 더해 갈수록 우라늄의 제염양은 지수함수적으로 감소하는 경향을 나타내었으며, 화학양론적으로 제거된 우라늄에 비하여 투여된 ${Na_2}{CO_3}$의 양은 과다함을 나타내었다. 이러한 결과들에 의하면, 공정최적화를 통하여 ${Na_2}{CO_3}$의 투여량 감축, 세척폐액의 감량, 제염단계 축소 등을 꾀할 수 있을 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.109-114
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• 2020

This work presents the results of laboratory scale tests of the CARBOFLUOREX (CARBOnate FLUORide EXtraction) process - a novel technology for the recovery of U and Pu from the solid fluorides residue (fluorination ash) of Fluoride Volatility Method (FVM) reprocessing of spent nuclear fuel (SNF). To study the oxidative leaching of U from the fluorination ash (FA) by Na₂CO₃ or Na₂CO₃-H₂O₂ solutions followed by solvent extraction by methyltrioctylammonium carbonate in toluene and purification of U from the fission products (FPs) impurities we used a surrogate of FA consisting of UF₄ or UO₂F₂, and FPs fluorides with stable isotopes of Ce, Zr, Sr, Ba, Cs, Fe, Cr, Ni, La, Nd, Pr, Sm. Purification factors of U from impurities at the solvent extraction refining stage reached the values of 10⁴-10⁵, and up to 10⁶ upon the completion of the processing cycle. Obtained results showed a high efficiency of the CARBOFLUOREX process for recovery and separating of U from FPs contained in FA, which allows completing of the FVM cycle with recovery of U and Pu from hardly processed FA.

• Nuclear Engineering and Technology
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• 제34권1호
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• pp.80-89
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• 2002

A laboratory investigation of the behavior of radioactive metals under the various waste combustion atmospheres was conducted to predict the parameters that influence their partitioning behavior during waste incineration. Neodymium, samarium, cerium, gadolinium, cesium and cobalt were used as non-radioactive surrogate metals that are representative of uranium, plutonium, americium, curium, radioactive cesium, and radioactive cobalt, respectively. Except for cesium, all of the investigated surrogate metal compounds converted into each of their stable oxides at medium temperatures from 400 to 90$0^{\circ}C$, under oxygen- deficient and oxygen-sufficient atmospheres (0.001-atm and 0.21-atm $O_2$). At high temperatures above 1,40$0^{\circ}C$, cerium, neodymium and samarium in the form of their oxides started to vaporize but the vaporization rates were very slow up to 150$0^{\circ}C$ . Inorganic chlorine (NaCl) as well as organic chlorine (PVC) did not impact the volatility of investigated Nd$_2$O$_3$, CoO and Cs$_2$O. The results of laboratory investigations suggested that the combustion chamber operating parameters affecting the entrainment of particulate and filtration equipment operating parameters affecting particle collection efficiency be the governing parameters of alpha radionuclides partitioning during waste incineration.

• 대한화학회지
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• 제26권3호
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• pp.160-164
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• 1982

단결정을 키우기에 적절한 용해도를 가진 $[U(PW_{11}O_{39})_2]^{10-}$의 구아니딘윰염을 합성하였다. 이 염 혹은 칼륨염을 사용하여 $[U(PW_{11}O_{39})_2]^{10-}$의 안정도를 용액의 pH의 함수로 조사하였으며, pH 3~7에서 안정함을 발견하였다. 이 영역에서 $PW_{11}O_{39}^{7-}$대 $U^{4+}$의 몰비가 2이상 되게 $PW_{11}O_{39}^{7-}$를 가하고 22.7kK band (${\varepsilon}$ 1030 M-1cm-1)띠의 세기를 측정함으로써 $U^{4+}$를 비색정량하는 방법을 개발하였다.$PW_{11}O_{39}^{7-}$ 를 사용하여 우라늄을 회수하는 방법을 개발하기 위해,$[U(PW_{11}O_{39})_2]^{10}$- 를 두 다른 방법으로 분해시켜 분리된$PW_{11}O_{39}^{7-}$ 를 정량하였다. $PW_{11}O_{39}^{7-}$의 회수율은 염기를 가해 분해시켰을 때 약 70%, $K_2S_2O_8$로 산화시켜 분해시켰을 때 약 80%이었다. 본 연구를 위해 $VOSO_4$를 이용한$PW_{11}O_{39}^{7-}$ 의 비색정량법도 개발하였다.

• Nuclear Engineering and Technology
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• 제51권5호
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• pp.1322-1332
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• 2019

In this paper, we systematically investigated the influence of some selected ligands on the U-phosphate precipitation induced by soil bacteria. These organics are widely ranging from acetate, lactate, salicylate and citrate to oxalate. The results revealed that uranium could be biomineralized on bacteria as $UO_2HPO_4{\cdot}4H_2O$ or $(UO_2)_3(PO_4)_2{\cdot}4H_2O$. The influence of organic ligands on the biomineralization had clear-cut correlations with its complexation abilities to uranyl. It was clearly found that the U-phosphate biomineralization was affected noticeably by the strong ligands (oxalate and citrate). Further study discovered that when the organic ligands were uncompetitive with biotic $PO_4^{3-}$ for uranyl, the transformation of uranyl species from ${\beta}-UO_2(OH)_2$ colloidal particles to free $UO_2^{2+}$-ligands ions could facilitate the U-phosphate biomineralization. However, when the organic ligands competed with biotic $PO_4^{3-}$ for uranyl, the U-phosphate biomineralization were inhibited. Our results highlight the importance of complex interactions of strong organic ligands with uranyl during the bacterial precipitation of U-P compounds and thus for the mobilization and immobilization of radio-nuclides in the nature.

• Nuclear Engineering and Technology
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• 제35권6호
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• pp.507-514
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• 2003

Recently dry decontamination/surface-cleaning technology using plasma etching has been focused in the nuclear industry. In this study, the applicability of this new dry processing technique are experimentally investigated by examining the etching reaction of $UO_2$, Co, and Mo in r.f. plasma with the etchant gas of $CF_4/O_2$ mixture. $UO_2$ is chosen as a representing material for uranium and TRU (TRans-Uranic) compounds while metallic Co and Mo are selected because they are the principal contaminants in the used metallic nuclear components such as valves and pipes made of stainless steel or inconel. Results show that in all cases maximum etching rate is achieved when the mole fraction of $UO_2\;in\;CF_4/O_2$ mixture gas is $20\%$, regardless of temperature and r.f. power. In case of $UO_2$, the highest etching reaction rate is greater than 1000 monolayers/min. at $370^{\circ}C$ under 150 W r.f. power which is equivalent to $0.4{\mu}m/min$. As for Co, etching reaction begins to take place significantly when the temperature exceeds $350^{\circ}C$. Maximum etching rate achieved at $380^{\circ}C\;is\;0.06{\mu}m/min$. Mo etching reaction takes place vigorously even at relatively low temperature and the reaction rate increases drastically with increasing temperature. Highest etching rate at $380^{\circ}C\;is\;1.9{\mu}m/min$. According to OES (Optical Emission Spectroscopy) and AES (Auger Electron Spectroscopy) analysis, primary reaction seems to be a fluorination reaction, but carbonyl compound formation reaction may assist the dominant reaction, especially in case of Co and Mo. Through this basic study, the feasibility and the applicability of plasma decontamination technique are demonstrated.

• 미생물학회지
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• 제38권2호
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• pp.133-138
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• 2002

금속 이온 환훤 세균에 의한 철(III)환원은 생물지구화학적 물질순환(biogeochemical cycle)에 무척 중요하다. 이는 크롬(Ⅵ)이나 우라늄(Ⅵ)과 같은 독성 중금속 물질의 환원과 유기물질의 산화에 모텔이 되기 때문이다. 총 37균주의 Fe (III)환원 세균을 소양호와 천호지의 저질토에서 각각 분리하였다. 두 정점 중 초기 Fe (II)의 함유량이 가장 높았던 것은 소양호의 저질토였으나 Fe (III)환훤능은 반대로 가장 낮은 Fe (II)함유량을 보여 주었던 천호지가 높게 나타났다. 또한 분리한 균주 중 천호지에서 분리한 균주 C2와 C3가 가장 높은 Fe (III) 환훤능을 보여 주었으며 이 균주를 이용하여 다양한 전자 공여체의 이용 여부를 실험하였다. Glucose, yeast extract, acetate, ethanol, toluene등을 이용하여 실험한 결과 두 균주 모두 glucose와 yeast extract만을 전자 공여체로 이용하였다. 또한 전자 수용체로 토양에 광범위하게 존재하는 humid acid와 nitrate를 이용하였으며 수율이 높은 nitrate reduction에 의해 환원되었던 humic acid가 다시 재 산화되는 것을 관촬할수 있었다. 활성능이 우수한 균주 C2와C3의 165S rRNA유전자 분석 결과에 의하면 Aeromonas hydrophila와 95%의 유사성을 보여주었다.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1300-1309
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• 2023

Simulated debris was synthesized using UO₂, Zr, and stainless steel and a heat treatment method under inert or oxidizing conditions. The primary U solid phase of the debris synthesized at 1473 K under inert conditions was UO₂, whereas a (U, Zr)O₂ solid solution formed at 1873 K. Under oxidizing conditions, a mixture of U₃O₈ and (Fe, Cr)UO₄ phases formed at 1473 K, whereas a (U, Zr)O_2+x solid solution formed at 1873 K. The leaching behavior of the fission products from the simulated debris was evaluated using two methods: the irradiation method, for which fission products were produced via neutron irradiation, and the doping method, for which trace amounts of non-radioactive elements were doped into the debris. The dissolution behavior of U depended on the properties of the debris and aqueous solution for immersion. Cs, Sr, and Ba leached out regardless of the primary solid phases. The leaching of high-valence Eu and Ru ions was suppressed, possibly owing to their solid-solution reaction with or incorporation into the uranium compounds of the simulated debris.

• 미생물학회지
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• 제39권3호
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• pp.175-180
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• 2003

Shewanella putrefaciens DK-1은 그람음성, 통성 혐기성 세균으로 $NO_{3}$, Fe(III), Mn(IV), humic acid와 같은 다양한 전자수용체를 이용한다. S. putrefaciens DK-1의 전자공여체의 이용능력은 제한적이며, lactate나 formate는 좋은 전자공여체로 이용되지만 acetate나 toluene은 이용하지 못하였다. 다양한 전자수용체간의 경쟁을 살펴보기 위해 전자수용체로 Fe(III)와 같이 $NO_{3}^{-}$, $NO_{2}^{-}$를 넣어 주었을 매 Fe(III)의 환원은 저해되었다. 또한 5. putrefaciens DK-1은 전자수용체로 토양에 광범위하게 존재하는 humic acid를 이용하였으며, 환원된 humic acid는 질산염에 의해서 다시 산화되었다. Fe(III) 환원능이 있는 환경 시료를 이용하여 탄소, 질소, 인과 같은 제한 요인이 Fe(III) 환원세균의 활성에 미치는 효과를 조사하였다. 천호지의 저질토와 대호의 농토에 각각 탄소원, 질소원, 인을 첨가해 주었을 경우 S. putrefaciens DK-1과 탄소원을 동시에 첨가해 주었을 때 가장 높은 철 환원능을 보여주었다.

• 한국재료학회:학술대회논문집
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• 한국재료학회 2011년도 춘계학술발표대회
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• pp.15-15
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• 2011

As you know, boron compounds, borax ($Na_2B_4O_5(OH)_4{\cdot}8H_2O$) etc. were known thousands of years ago. As for natural boron, it has two naturally occurring and stable isotopes, boron 11 ($^{11}B$) and boron 10 ($^{10}B$). The neutron absorption $^{10}B$ is included about 19~20% with 80~81% $^{11}B$. Boron is similar to carbon in its capability to form stable covalently bonded molecular networks. The mass difference results in a wide range of ${\beta}$ values between the $^{11}B$ and $^{10}B$. The $^{10}B$ isotope, stable with 5 neutrons is excellent at capturing thermal neutrons. For example, it is possible to decrease a thermal neutron required for the nuclear reaction of uranium 235 ($^{235}U$). If $^{10}B$ absorbs a neutron ($^1n$), it will change to $^7Li+^1{\alpha}$ (${\alpha}$ ray, like $^4He$) with prompt ${\gamma}$ ray from $^{11}B$ $^{11}B$ (equation 1). $$^{10}B+^1n\;{\rightarrow}\;^{11}B\;{\rightarrow}\; prompt \;{\gamma}\;ray (478 keV), \;^7Li+4{\alpha}\;(4He)\;\;\;\;{\cdots}\; (1)$$ If about 1% boron is added to stainless steel, it is known that a neutron shielding effect will be 3 times the boron free steel. Enriched boron or $^{10}B$ is used in both radiation shielding and in boron neutron capture therapy. Then, $^{10}B$ is used for reactivity control and in emergency shutdown systems in nuclear reactors. Furthermore, boron carbide, $B_4C$, is used as the charge of a nuclear fission reaction control rod material and neutron cover material for nuclear reactors. The $B_4C$ powder of natural B composition is used as a charge of a control material of a boiling water reactor (BWR) which occupies commercial power reactors in nuclear power generation. The $B_4C$ sintered body which adjusted $^{10}B$ concentration is used as a charge of a control material of the fast breeder reactor (FBR) currently developed aiming at establishment of a nuclear fuel cycle. In this study for new boron compound, silicon boride ceramics for capturing thermal neutrons, preparation and characterization of both silicon tetraboride ($SiB_4$) and silicon hexaboride ($SiB_6$) and ceramics produced by sintering were investigated in order to determine the suitability of this material for nuclear power generation. The relative density increased with increasing sintering temperature. With a sintering temperature of 1,923 K, a sintered body having a relative density of more than 99% was obtained. The Vickers hardness increased with increasing sintering temperature. The best result was a Vickers hardness of 28 GPa for the $SiB_6$ sintered at 1,923K for 1 h. The high temperature Vickers hardness of the $SiB_6$ sintered body changed from 28 to 12 GPa in the temperature range of room temperature to 1,273 K. The thermal conductivity of the SiB6 sintered body changed from 9.1 to 2.4 W/mK in the range of room temperature to 1,273 K.