• Koreanishche Zeitschrift fur Deutsche Sprachwissenschaft
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• v.3
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• pp.95-120
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• 2001

Modalpartikel-Kombinationen wurden bisher in der Forschung kaum behandelt. Modalpartikeln stehen immer im Mittelfeld eines Satzes. Innerhalb des Mittelfeldes aber ist ihre Position variabel. Nur deshalb sind auch Modalpartikel-Kombinationen $m\"{o}glich$, bei denen zwischen den beiden Partikeln ein oder mehrere Lexeme auftreten $k\"{o}nnen$.. Diese Art von Kombination soll hier 'offene Kombination' genannt werden im Gegensatz zu den 'geschlossenen Kombinationen' bei denen die eine Modalpartikel unmittelbar auf die andere folgt. Die Stellung der beiden Modalpartikeln bei einer offenen Kombination ist im Satz nicht beliebig, und deshalb ist auch das, was zwischen zwei Modalpartikeln steht, gewissen Beschrankungen unterworfen. Vor allem die Position der zweiten bzw. letzten Modalpartikel im Satz $h\"{a}ngt$ von der Thema-Rhema-Gliederung ab. Die geschlossenen Varianten der Modalpartikel- Kombinationen sind das ein Indiz $f\"{u}r$ die Verfestigung. Es handelt sich eben nicht mehr nur um das $zuf\"{a}llige$ Auftreten zweier partikeln irn selben Satz, sondem irn vielen $F\"{a}llen$ um eine feste Einheit, deren Bedeutung allerdings immer noch aus der Bedeutung der Einzelbestandteile zusamrnengesetzt werden kann. Kornbinationen von Modalpartikeln sind also als ein weiteres wichtiges Mittel zur Gestaltung eines Dialogs und damit zur Ausgestaltung des Kontakts der $Gespr\"{a}chspartner$ untereinander zu sehen.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.2
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• pp.179-186
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• 2006

Chemical wastes are generated from nuclear facilities and R&D laboratories, but the uranium concentration in the final dried cake is evaluated into 11.2 Bq/g, which exceeds the exemption level of 10 Bq/g for each U isotopes, so the cake is categorized into a radioactive waste. Acid dissolution was applied to extract uranium from the waste sludge, and uranium adsorption on the dissolved solution was experimented by using IRN-77 and Diphosil bead. A large amount of resin was required to get above 80% of uranium removal, which was found to be due to a large amount of metal ions simultaneously dissolved from the precipitates with uranium. As an alternative method, acid dissolution is applied to the dewatered wet cake of the sludge, and the natural evaporation method is adopted for the dissolved solution. The uranium concentration of the dissolved solution was estimated to be 6.97E-01 Bq/ml, and the specific activity of the final waste sheets is evaluated to be 4.3 Bq/g. These results lead to the suggestion that the application of acid dissolution to the wet cake and the natural evaporation for the dissolved solution is an effective treatment method for chemical wastes containing uranium.

• Journal of Radiation Protection and Research
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• v.27 no.1
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• pp.27-35
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• 2002

Characteristics of Amberlite IRN 77, a cation exchange resin, and the mechanisms of its adsorption equilibria with Co(II), Ni(II), Cr(III) and Fe(III) ions were investigated for the application of the demineralizing process in the primary coolant system of a pressurized water reactor (PWR). The optimum dosage of the resin for removal of the dissolved metal ions at $200mgL^{-1}$ was 0.6 g for 100 mL solution. Most of each metal ion was adsorbed onto the resin in an hour from the start of the reaction. Each metal adsorption onto the resin could be well represented by Langmuir isotherms. However, in the case of Fe(III) adsorption, continuous formation of Fe-oxide or -hydroxide and its subsequent precipitation inhibited the completion of the equilibrium between the metal and the adsorbent Cobalt(II) and Ni(II), which have an equivalent electrovalence, were adsorbed to the resin with a similar adsorption amount when they coexisted in the solution. However, Cr(III) added to the solution competitively replaced Co(II) and Ni(II) which were already adsorbed onto the resin, resulting in desorption of these metals into the solution. The result was likely due to a higher adsorption affinity of Cr(III) than Co(II) and Ni(II). This implies that the interactively competitive adsorption of multi-cations onto the resin should be fully considered for an efficient operation of the demineralizing ion exchange process in the primary coolant system.

• Korean Journal of Computational Design and Engineering
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• v.16 no.1
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• pp.73-81
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• 2011

This study aims to study IFD based IFC application, and API technology were examined for extending $IFC2{\times}4$ information by using IFD libraries. According to this, information exchange scenarios for Open BIM were established with IFD application. And necessary standard elements for introduction of IFD were introduced and the templates of object and property information were suggested for realization.

• Journal of Radiation Protection and Research
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• v.29 no.1
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• pp.1-8
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• 2004

Diphosil, a new version of the organic-inorganic composite resin developed by ANL has a structure of the chelating diphosphonic acid groups grafted to a silica support. To apply Diphosil for the treatment of liquid radioactive waste from nuclear power plants, the adsorption equilibrium and column experiments were carried out for the main radionuclides, $^{137}Cs\;and\;^{60}Co$, in the liquid radwaste stream. Through the adsorption equilibrium experiments, the removal efficiencies of $^{137}Cs\;and\;^{60}Co$, and the effects of non-radioactive ions on the removal efficiency have been measured in various conditions using radiotracers. The breakthrough curves for the tested tracers were obtained from the laboratory scale column tests using the simulated liquid radioactive waste. In addition, the removal capacity of Diphosil is compared with that of Amberlite IRN 77 resin, generally used in nuclear power plants.

• Applied Chemistry for Engineering
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• v.4 no.1
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• pp.171-177
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• 1993

In decontamination process to remove radioactive materials of reactor cooling system, the metal ions dissolved by organic acids in decontamination solution are separated by use of ion exchange resin in the column. However, organic acids in decontamination solution decrease the apparent affinity of the resin to metal ions. In light of this, some experiments were carried out on the Amberlite IRN-77 cation resin with cobalt and iron to gain a better understanding of the complexation effects on the ion exchange process. Experimental results showed that EDTA among organic acids used as chemical decontaminants predominantly caused reduction of ion exchange capacity of cobaltous ion to resin since this reagent formed the complex with the cobaltous ion stronger than that with the ferrous ion. In contrast, the effects of oxalic acid and citric acid were found to be negligible. And, single and two-component nonlinear equilibrium relationships of the metal ions were established using experimental data.

• Nuclear Engineering and Technology
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• v.23 no.4
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• pp.374-386
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• 1991

Various factors affecting the teachability of Cs-137 in cement matrix have been investigated. Factors investigated include such as pressure curing, vibration curing, pressure leaching, the effect of the clay addition, ion-exchange resin(IRN-77) addition, and $CO_2$or air injection. Leaching experiments were conducted by the method recommended by IAEA. To analyze the experimental results, pore structure analysis of cement matrices was carried out by BET method. Cement matrices may not contact directly with underground water in real repository, since the surroundings of disposed drums are filled with backfill. Thus, the effect of backfill to the teachability has been investigated. The well-known diffusion theory was utilized to predict long term leach rate and cumulative fraction leached of Cs-137 or non-radioactive species.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.415-420
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• 1998

시판중인 대표적 유·무기이온교환수지를 이용하여 방사성폐액의 주 방사성핵종인 코발트와 세슘에 대하여 방사성패액에 함유되어 있는 대표적 일반이온인 나트륨이온이 이들의 이온교환에 미치는 영향을 분석하였다. 나트륨 존재 하에서 세슘이온에 대한 선택도와 수지단위 부피당 폐액 처리 부피는 무기이온교환수지인 DT 30과 Durasil 230이 가장 높으며 반면에 유기이온교환수지는 두 수치 모두 낮아서 유기이온교환수지는 저농도의 나트륨 이온을 갖는 증발기 응축수의 처리에는 적합하나 나트륨이온의 농도가 비교적 높은 폐액처리에는 적합하지 않으며, 또한 코발트 제거 면에서는 무기이온교환수지인 DT 10 보다 유기이온교환수지인 Amberlite IRN 77이 바람직하다는 결론을 얻었다.

• JSTS:Journal of Semiconductor Technology and Science
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• v.11 no.4
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• pp.309-317
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• 2011

This paper describes a baseband analog (BBA) chain for wireless local area network (WLAN) applications. For the given specifications of the receiver BBA chain, the optimum allocation of the gain and filter rejection of each block in a BBA chain is achieved to maximize the SFDR. The fully integrated BBA chain is fabricated in 0.13 ${\mu}m$ CMOS technology. An input-referred third-order intercept point (IIP3) of 22.9 dBm at a gain of 0.5 dB and an input-referred noise voltage (IRN) of 32.2 nV/${\surd}$Hz at a gain of 63.3 dB are obtained. By optimizing the allocation of the gain and filter rejection using the proposed design methodology, an excellent SFDR performance of 63.9 dB is achieved with a power consumption of 12 mW.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.345-349
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• 1997

고준위 방사성 액체폐기물에서 얻어지는 백금족 금속(Pd, Rh, Ru) 들의 분리 및 정제방법으로 강염기성 음이온교환수지를 사용하여본 결과 상용 수지중에서 Dowex 1 $\times$ 8 이 IRN-78 에 비하여 저 농도의 질산 농도에서 Pd(II) 의 분리 및 정제시 우수한 흡착성을 보여 주었으며 Rh(III) 의 흡착은 Pd(II) 의 것보다 훨씬 낮은 값을 보여 주었다. 이 수지들의 백금족 금속에 대한 흡착성을 문헌에 보고된 실험 결과들과 비교 검토하여 본 바 이온 그룹으로 3급 및 4급 Benzimidazole을 가지는 수지에 비하여 훨씬 낮은 값을 나타내었다. 따라서 실용성이 큰 강염기성 음이온수지로서는 Benzimidazole과 같은 혼합 아민 그룹을 지닌 수지가 가장 접합할 것으로 전망되었다.