카드뮴-113 NMR을 이용한 폴리아크릴산의 카드뮴(Ⅱ) 이온에 대한 결합자리의 특성연구

정근호,구자응,신현상,문희정,Chung, Kun Ho,Koo, Ja-Eung,Shin, Hyun Sang,Moon, Hichung 대한화학회 1996 대한화학회지 Vol.40 No.1

The cadmium(Ⅱ)-carboxylate complexes of monocarboxylates and poly(acrylic acid) (PAA) in an aqueous solution were investigated using 113Cd NMR spectroscopy. From these spectral data the chemical shifts of the monocarboxylate (e.g. acetate, benzoate and propanoate) complexes of Cd(Ⅱ) were evaluated (CdL+: -22 to -24 ppm range; CdL2: -39 to -40 ppm range; L: carboxylate). The chemical shift of cadmium(Ⅱ) bound on PAA changed in value from -36.6 to -38.2 ppm when the [PAA]/[Cd] ratios were varied from 12 to 118 eq/mol at a constant pH of 6. The 113Cd chemical shift was sensitive to the change in solution pH: the chemical shift changed from 1.6 to -37.6 ppm when the pH was rasied from 1 to 6 at a constant [PAA]/[Cd] ratio of 39 eq/mol. These results show that under these conditions, the dominant species formed in solution is 1 : 2 complex (CdL2), and 1 : 1 complex (CdL+) is only formed at low pH, when polyanion concentration is low. 카드뮴-113 NMR을 이용하여 수용액속에서 카드뮴 이온과 유기산(아세트산, 벤조산 및 프로판산)과의 결합 특성을 알아보았고 여기서 얻어진 결과를 폴리아크릴산(PAA)의 결합자리의 특성연구에 응용하였다. 유기산에 결합된 카드뮴 화합물의 카드뮴-113 NMR 화학적이동 결과 분석으로부터, $CDL^+$와 $CDL_2$(L:카르복실기) 화학종에 해당하는 화학적이동값은 각각 -22에서 -24ppm과 -39에서 -40ppm의 범위를 나타냈다. 카드뮴과 폴리아크릴산 화합물에서는 폴리아크릴산 대 카드뮴의 농도비를 12에서 118eq/mol로 증가시킬 때 화학적 이동값이 -36.6ppm에서 -38.2ppm으로 변하였다. 또한, 폴리아크릴산 대 카드뮴의 농도비를 고정시키고 ([PAA]/[Cd] = 39ep/mol) 용액의 pH를 1에서 6까지 변화시킬 때 화학적이동값은 1.6ppm에서 -37.6ppm으로 변하였다. 이 결과는 폴리아크릴산 대 카드뮴의 농도비 변화 실험에서 주화학종은 1:2 착물($CdL_2$)이고 농도비가 증가하면 1:2 착물형성도 증가하는 것을 보여준다.또한, 낮은 pH에서는 1:1착물($CdL^+$)이 우세하고 pH가 증가하면서 1:2 착물($CdL_2$)이 증가한다는 것을 알 수 있었다.

[환경] 겔 여과 크로마토그래피에 의한 토양 풀빅산의 분자량 분획 및 형광특성 분석

정근호(Kun-Ho Chung),신현상(Hyun-Sang Shin),이완로(Wanno Lee),조영현(Yeong-Hyun Cho),최근식(Geun-Sik Choi),이창우(Chang-Woo Lee) 한국분석과학회 2004 분석과학 Vol.17 No.2

해체 콘크리트 폐기물에 포함된 $^{55}Fe$와 $^{63}Ni$ 방사능 분석

강문자,정근호,홍상범,최근식,이창우,Kang, Mun-Ja,Chung, Kun-Ho,Hong, Sang-Bum,Choi, Geun-Sik,Lee, Chang-Woo 한국방사성폐기물학회 2007 방사성폐기물학회지 Vol.5 No.1

Combined method of extraction chromatography and liquid scintillation analysis was established for determinating $^{55}Fe\;and\;^{63}Ni$ radioactivity in solid samples. Activated concrete wastes generated from dismantling KRR-2 were analysed. The sequential separation including precipitation and extraction chromatography resulted in the above 90% chemical recoveries of Fe. Above 62% recoveries of Ni were obtained by this procedure exception to 43.6 and 46.5% recoveries. The seperation and counting procedure was also confirmed with spiked samples of known quantity. The measured and spiked quantity were agreed with the 3.7% and 0.7% variations in the $^{55}Fe\;and\;^{63}Ni$ experiments, respectively. The radioactivities of $^{55}Fe$ in the dismantled concretes are shown from below MDA to maximum 362 Bq/g. The radioactivities of $^{63}Ni$ in all concrete samples are below MDA. The $^{63}Ni$ doesn't exist in dismantled concretes from KRR-2. The radioactivity of $^{55}Fe$ is decreased rapidly as the sampling depth is increased from the concrete surface.

감마분광분석을 이용한 원료물질 및 공정부산물 중 ²²⁶Ra 신속분석방법

임충섭,정근호,김창종,지영용,Lim, Chung-Sup,Chung, Kun-Ho,Kim, Chang-Jong,Ji, Young-Yong 한국방사성폐기물학회 2017 방사성폐기물학회지 Vol.15 No.1

A gamma-ray peak of $^{226}Ra$ (186.2 keV) overlaps with one of $^{235}U$ (185.7 keV) in a gamma-ray spectrometry system. Though reference peaks of $^{235}U$ can be used to correct the peak interference of $^{235}U$ in the analysis of $^{226}Ra$, this requires a complicated calculation process and a high limit of quantitation. On the other hand, evaluating $^{226}Ra$ using the correction constant in the overlapped peak can make a rapid measurement of $^{226}Ra$ without the complicated calculation process as well as overcome the disadvantage in the indirect measurement of $^{214}Bi$, which means the confinement of $^{222}Rn$ gas in a sample container and a time period to recover the secular equilibrium. About 93 samples with 6 species for raw-materials and by-products were prepared to evaluate the activity of $^{226}Ra$ using the correction constant. The results were compared with the activity of $^{214}Bi$, which means the indirect measurement of $^{226}Ra$, to validate the method of the direct measurement of $^{226}Ra$ using the correction constant. The difference between the direct and indirect measurement of $^{226}Ra$ was generally below about ${\pm}20%$. However, in the case of the phospho gypsum, a large error of about 50% was found in the comparison results, which indicates the disequilibrium between $^{238}U$ and $^{226}Ra$ in the materials. Application results of the contribution ratio of $^{226}Ra$ were below about ${\pm}10%$. The direct measurement of $^{226}Ra$ using the correction constant can be an effective method for its rapid measurement of raw materials and by-products because the activity of $^{226}Ra$ can be produced with a simple calculation without the consideration of the integrity of a sample container and the time period to recover the secular equilibrium.

감마분광분석을 이용한 ²²⁶Ra의 직접 측정방법에 대한 적용성 평가

지영용,정근호,임종명,김창종,장미,강문자,박상태,우주희,구본철,서보균,Ji, Young-Yong,Chung, Kun Ho,Lim, Jong-Myoung,Kim, Change-Jong,Jang, Mee,Kang, Mun Ja,Park, Sang Tae,Woo, Zuhee,Koo, Boncheol,Seo, Bokyun 한국방사성폐기물학회 2014 방사성폐기물학회지 Vol.12 No.2

HPGe 감마선 검출기를 이용하여 $^{226}Ra$의 방사능을 직접 측정방법의 경우, $^{226}Ra$의 186.21 keV 감마선이 $^{235}U$에서 방출되는 185.7 keV 감마선에 의한 간섭을 받기 때문에 피크면적의 계산에서 반드시 보정이 필요하다. 비록 분해능이 아주 우수한 HPGe 검출기를 사용한다 하더라도 그리고 분광시스템의 채널수를 최대로 늘린다고 할지라도 약 0.5 keV 차이의 두 감마선 피크를 분리해 내기란 현실적으로 어려운 일이다. 본 연구에서는 감마분광분석을 이용한 $^{226}Ra$의 직접 측정방법에 대한 적용성을 평가하기 위하여, 여러 가지 간섭피크 보정들을 이용한 직접 측정방법을 조사하였다. 이를 원료물질 및 공정부산물 시료들에 적용함으로써 직접 측정방법들에서 그 측정 불확도, 직선성 및 적용범위 등을 평가하였다. 최종적으로 방사평형 관계를 이용하여 $^{226}Ra$의 방사능을 측정하는 간접 측정방법으로부터 얻은 $^{214}Pb$ 및 $^{214}Bi$의 결과를 직접 측정방법의 결과와 비교함으로써 최적의 측정방법을 유도하였다. In the case of the direct measurement of $^{226}Ra$ using a HPGe gamma-ray spectrometer, the interference between gammarays with 186.21 keV of $^{226}Ra$ and 185.7 keV of $^{235}U$ should be corrected to calculate the net peak area in the energy spectrum. In general, it is very difficult to conduct peaks stripping with difference of about 0.5 keV, although a HPGe with the superior resolution is applied and the maximum channels is applied to the spectrometer. In this study, several interference correction techniques in the direct measurement were surveyed to evaluate the feasibility for the measurement of $^{226}Ra$ using the gamma-ray spectrometery. Applying the interference corrections to the analysis of raw materials and by-products, the method validation for the direct measurement of $^{226}Ra$ was conducted by evaluating the measurement uncertainty, linearity, and range. As a result, the optimum method of the interference correction was selected by comparing with the indirect measurement of which progenies of $^{226}Ra$, such as $^{214}Pb$ and $^{214}Bi$, were analyzed in the secular equilibrium state.

국내 원자력 발전소 주변 토양 휴믹산의 추출 및 특성 규명

이창훈,신현상,정근호,조영현,이창우,Lee, Chang-Hoon,Shin, Hyun-Sang,Chung, Kun-Ho,Cho, Young-Hyun,Lee, Chang-Woo 대한방사선방어학회 2003 방사선방어학회지 Vol.28 No.3

본 연구에서는 국내 원자력발전소가 위치한 지역의 토양(영광, 울진, 고리, 고성, 월성)에 존재하는 휴믹산(HA)을 추출하여 각 시료의 원소성분 및 분광학적 방법(UV/Vis, IR, CPMAS $^{13}C$ NMR)을 이용한 물질 특성을 조사하였고, Aldrich HA과 함께 비교 분석하였다. 분자량 크기 분포의 차이는 한외여과법을 이용하여 조사하였다. 원소분석 결과, 울진 지역의 HA에서 가장 높은 산소 함량비를 보였으며, 고리와 고성지역의 HA에서 상대적으로 낮은 산소 함량비를 보였다(O/C: 0.51(UJHA) vs. 0.43(KRHA), 0.46(KSHA)). 분자량 크기 분포는 울진과 영광 지역의 HA가 고리와 고성 지역의 HA에 비하여 30,000 daltons이상의 고분자가 더 높게 존재함을 알 수 있었다. CPMAS $^{13}C$ NMR, UV/Vis., IR 등의 분광학적 특성분석 결과, 울진과 영광 지역의 HA가 고리, 고성 및 월성 지역의 HA에 비하여 상대적으로 높은 방향족성(aromaticity)과 산소 포함 작용기의 함량이 높은 특성을 보였다. 이상의 결과로 볼 때, 울진과 영광지역의 HA가 상대적으로 더 높은 휴믹화(humification) 단계의 물질 특성을 가짐을 알 수 있었으며, 금속이온과의 반응성이 더 높을 것으로 예측된다. Humic acids present in the soils at the vicinity of domestic atomic power plants(NPPs), located in Yeongkwang(YK), Uljin(UJ), Kori(KR), Koseong(KS), Wolseong(WS) area were isolated, and characterized using elemental analysis and UV/Vis, IR, CPMAS $^{13}C$ NMR spectroscopic methods. The characteristics were compared with one another and with commercial humic acid (Aldrich Co.). Molecular size distributions of the humic acids were determined using a stirred cell ultrafiltration technique. The results of elemental analysis showed that soil humic acid from UJ contains higher oxygen content than humic acids from KR and KS (O/C ratios: 0.51 (UJHA) us. 0.45(KRHA), 0.43(KSHA)). The molecular size distribution revealed that the soil humic acids of UJ and YK contained a higher percentage of larger molecules of > 30,000 daltons, compared to those of KR and KS. The spectral features obtained from UV/vis., IR and CPMAS $^{13}C$ NMR showed that the aromatic character and oxygen containing functional groups in the humic acids from UJ and YK were relatively higher than those of KR and KS. These results indicate that the soil humic acids from UJ and YK were in a higher degree of humification, which may suggest higher affinity of the humic acids with radionuclides released in the soil environments.

실용적이고 간단한 환경시료의 감마핵종 자체흡수보정 방법

이완로,이행필,정근호,최근식,조영현,이창우,정형욱,이은주,소유섭,이종옥,Lee, Wan-No,Lee, Haeng-Pil,Chung, Kun-Ho,Cho, Young-Hyun,Choi, Geun-Sik,Lee, Chang-Woo,Chung, Hyung-Wook,Lee, Eun-Ju,Sho, You-Sup,Lee, Jong-Ok 대한방사선방어학회 2006 방사선방어학회지 Vol.31 No.1

A self-absorption correction is important issue for the exact radioactivity determination of gamma emitting radionuclides in environmental samples which have the range of apparent density from $0.3g/cm^3$ up to $1.5g/cm^3$. In this paper, a practical and simple method without radioactive standard solutions having various densities is proposed for the self-absorption correction of environmental samples by a developed outside beaker surrounding Marinelli beaker. For the densities of 0.8, 1.0, $1.3g/cm^3$, the corrected efficiencies by the new method and the measured those by radioactive standard solutions of the three densities showed good agreement within 4 %. $0.3g/cm^3$ 에서 $1.5g/cm^3$까지 다양한 겉보기 밀도를 갖는 감마방출핵종 환경시료의 정확한 방사능 분석을 위해서 자체흡수보정(self-absorption correction)은 중요한 문제이다. 방사선 표준선원을 밀도별로 제작할 필요없이 마리넬리 비커를 감싸는 외부용기를 새롭게 제작하여 실용적이면서 간단한 자체흡수보정방법을 본 논문에서 제시하였다. 밀도 0.8, 1.0, $1.3g/cm^3$ 대해서 새로운 방법을 이용하여 자체흡수보정을 한 효율들과 밀도별로 직접 표준선원용액을 만들어 측정한 효율값이 4 % 이내에서 일치하였다.

연구로 2호기 수조 콘크리트의 $^3H$ 및 $^{14}C$ 공간분포

홍상범,김희령,정근호,강문자,정경환,정운수,박진호,Hong, Sang-Bum,Kim, Hee-Reyoung,Chung, Kun-Ho,Kang, Mun-Ja,Jeong, Gyeong-Hwan,Chung, Un-Soo,Park, Jin-Ho 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.4

The depth distributions of total $^3H$ and $^{14}C$ activities were characterized for the activated shielding concrete from a decommissioning of KRR-2 using the commercially available tube furnace and a liquid scintillation counter. The correlation of measurement results between $^3H,\;^{14}C$ and gammer emitter was evaluated to apply for estimating radionuclide inventory of the concrete waste generated from decommissioning KRR-2. The detection limits for $^3H$ and $^{14}C$ are 0.048 and 0.028 Bq/g respectively. The specific activities of the $^3H$ and $^{14}C$ tend to decrease exponentially as the depth of the concrete becomes deeper from the surface. In addition, the $^3H$ and $^{14}C$ activities were in good correlation with the $^{60}CO$ activities analysed for the shielding concrete of KRR-2.

현장검출기에 저장된 백업데이터를 무선통신방식으로 자동 복원하는 실시간 환경선량 감시 시스템

이완로,김은한,정근호,조영현,최근식,이창우,박기현,김윤구,Lee, Wan-No,Kim, Eun-Han,Chung, Kun-Ho,Cho, Young-Hyun,Choi, Geun-Sik,Lee, Chang-Woo,Park, Ki-Hyun,Kim, Yun-Goo 대한방사선방어학회 2003 방사선방어학회지 Vol.28 No.3

환경선량변동을 실시간으로 모니터링하기 위해서 원자력연구소 부지 주변에 온라인 감시시스템이 운영중인데, 현장에 설치된 전리함 검출기에 의해서 측정된 자료는 모뎀을 통해 무선전송방식으로 중앙제어실에 실시간으로 저장된다. 무선 송수신 방식은 전송, 처리 및 저장에 경제적이고 효과적이지만 통신 장애시 현장감시장치에 저장된 백업데이터를 가져오지 못해서 결국 데이터가 손실될 우려가 있다 물론 버퍼에 저장된 선량값을 디스켓 및 다른 off-line으로 복원이 가능하지만 이럴 경우 온라인으로 운영되는 시스템에 과거데이터를 처리해야 하므로 복잡하고 실시간으로 처리 할 수가 없다. 본 연구에서는 기존 감시시스템 중 신호처리 부분과 운영 소프트웨어를 새롭게 개발해서, 현장에 설치된 감시기와 중앙처리 장치의 시각을 매일 자동으로 동기화시키고 이를 이용해서 현장감시장치에 저장된 백업데이터를 자동으로 복원시켰다. 새로 개발된 방식을 이용할 경우 34시간이내에서 통신장애로 수신하지 못한 백업데이터를 자동으로 복원할 수 있고, 복원된 데이터를 현재시각의 데이터와 함께 실시간으로 디스플레이 할 수 있게 하였다. An environmental radiation monitoring system based on high pressurized ionization chamber has been used for on-line gamma monitoring surrounding the KAERI (Korea Atomic Energy Research Institute), which transmits the dose data measured from ion chamber on the site via radio frequency to a central processing computer and stores the transmitted real-time data. Although communication using radio frequency has several advantages such as effective and economical transmission, storage, and data process, there is one main disadvantage that data loss during transmission often happens because of unexpected communication problems. It is possible to restore the loss data by off-line such as floppy disk but the simultaneous process and display of current data as well as the backup data are very difficult in the present on-line system. In this work, a new electronic circuit board and the operation software applicable to the conventional environmental radiation monitoring system are developed and the automatical synchronization of the ion chamber unit and the central processing computer is carried out every day. This system is automatically able to restore the backup data within 34 hours without additional equipments and also display together the current data as well as the transmitted backup data after checking time flag.

환경방사선감시기의 NaI(Tl) 검출기를 이용한 조사선량률 결정방법

지영용,이완로,최상도,정근호,강문자,최근식,Ji, Young-Yong,Lee, Wanno,Choi, Sang-Do,Chung, Kun Ho,Kang, Mun Ja,Choi, Geun-Sik 한국방사성폐기물학회 2013 방사성폐기물학회지 Vol.11 No.3

The energy band and the G-factor method were compared to determine the exposure rate from the measured spectrum using a NaI(Tl) scintillation detector. First, G-factors of a 3"${\Phi}X3$" NaI(Tl) detector mounted to a EFRD 3300, which means the environmental radiation monitor, in Korea Atomic Energy Research Institute (KAERI) were calculated for several directions of incident photons through the MCNP modeling, and the optimum G-factor applicable to that monitor was then determined by comparing the results both the energy band method and the G-factor method. The results for these spectrometric determinations were also compared with the dose rate from a HPIC radiation monitor around a EFRD 3300. The measured value at the EFRD 3300 based on a 3"${\Phi}X3$" NaI(Tl) detector was $7.7{\mu}R/h$ and its difference was shown about $3{\mu}R/h$, when compared with the results from a HPIC radiation moditor. Since a HPIC is known to be able to measure cosmic rays with the relatively high energy, the difference between them was caused by cosmic rays which were not detected in a 3"${\Phi}X3$" NaI(Tl) detector.