원자력 사고시 주민 보호조치 결정 지원을 위한 비상 환경감시

최용호,최근식,한문희,이한수,이창우,Choi, Yong-Ho,Choi, Geun-Sik,Han, Moon-Hee,Lee, Han-Soo,Lee, Chang-Woo 대한방사선방어학회 2005 방사선방어학회지 Vol.30 No.3

원자력 사고로 인한 비상시에는 적기에 주민 보호조치를 취해야 한다. 주민 보호조치에 대한 결정기준은 국제적으로 비용-이득 분석에 의해 산정된 일반개입준위와 일반조치준위를 사용토록 제안되어 있다. 운영개입준위는 이러한 일반준위를 직접 또는 쉽게 측정할 수 있는 물리량으로 나타낸 것이다. 비상시 보호조치의 필요성을 판단하기 위해서는 운영개입준위를 적용하고 수정하는 데 요구되는 환경감시 자료를 신속히 생산하는 것이 중요하다. 비상대응의 일환으로서 이를 위해 무슨 일들이 어떻게 수행되어야 하는지 고찰하였다. 비상시 환경감시를 효과적으로 수행하기 위해서는 평상시에 조직과 설비의 유지 관리, 각종 절차 수립, 지원용 전산체제 개발, 주기적인 교육과 훈련 등 철저한 준비가 필요하다. 일반개입준위와 운영개입준위에 관한 우리나라의 규정이 보완 또는 신설될 필요가 있음이 지적되었다. In a nuclear emergency, protective actions for the public should be taken in time. It is internationally proposed that generic intervention levels (GILs) and generic action levels, determined based on cost-benefit analyses, be used as the decision criteria for protective actions. Operational intervention levels (OILs) are directly or easily measurable quantities corresponding to these generic levels. To assess the necessity of protective actions in a nuclear emergency, it is important that the environmental monitoring data required for applying and revising OILs should be promptly produced. It is discussed what and how to do for this task in the course of the emergency response. For an emergency environmental monitoring to be performed effectively, a thorough preparedness has to be made including maintenance of the organization and equipments, establishment of various procedure manuals, development of a supporting computer system and periodical training and exercises. It is pointed out that Korean legal provisions concerning GILs and OILs need to be amended or newly established.

대구지역 대기환경용량 산정에 관한 연구

박명희 ( Myung Hee Park ),최근식 ( Geun Sik Choi ),정우식 ( Woo Sik Jung ),김해동 ( Hae Dong Kim ),이준수 ( Joon Soo Lee ) 한국환경과학회 2010 한국환경과학회지 Vol.19 No.10

This study aims to implement the modeling of selected substances for the evaluation of Atmospheric Environmental Capacity by means of the data of 2006 atmospheric pollution substance emissions. As a result, it turned out that the substance with the concentration higher than Atmospheric Environmental standard concentration was NO2, and 17.6% of the total regions researched turned out to exceed the standard concentration. In addition, set was the targeted amount to be reduced in the areas where the upper limit of emission per unit lattice was exceeded, and the model was adopted accordingly. As a result, it turned out that about 80% of the actual emission should be reduced to meet the 2006 Atmospheric Environmental standard over the Daegu. In reality, it is impossible to reduce 80% of the actual emission. Thus, the same ratio of reduction was applied in all of the Daegu regions, and the modeling was applied. The results are as follows: When 30% was reduced, the level went down to 50 ppb, which is as high as 2006 Atmospheric Environmental standard; when 50% was reduced, the level went down to 30 ppb, which is as high as 2007 Atmospheric Environmental standard.

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.

염화칼리와 석회의 동시살포가 주요 작물의 생육중에 침적한 $^{54}Mn,\;^{60}Co,\;^{85}Sr\;and\;^{137}Cs$의 뿌리흡수에 미치는 영향

최용호,조재성,이명호,최근식,이정호,Choi, Yong-Ho,Jo, Jae-Seong,Lee, Myung-Ho,Choi, Geun-Sik,Lee, Jeong-Ho 대한방사선방어학회 1995 방사선방어학회지 Vol.20 No.4

2년 간의 온실실험을 통하여 벼, 콩, 배추, 무의 생육초기에 $^{54}Mn,\;^{60}Co,\;^{85}Sr\;and\;^{137}Cs$의 혼합용액을 산성 양질사토로 상층부를 채운 재배강자내 담수 또는 토양의 표면에 가한 후 비료용 염화칼리와 소석회를 각각 $m^2$당 200g 및 83g 수준으로 동시에 처리하고 흡수억제 효과를 조사하였다. 칼리와 석회 처리시 각 핵종의 작물체 부위간 농도분포 및 작물에 따른 흡수양상의 변화는 대체로 무처리시와 비슷한 경향이었다. 토양-작물체간 핵종의 전이계수는 칼리와 석회 처리에 의해 벼에서는 $^{85}Sr$와 $^{137}Cs$, 배추에서는 네 핵종 모두, 무에서는 $^{54}Mn,\;^{60}Co,\;and\;^{137}Cs$의 경우 생육장해 없이 왜 크게 감소하였으나 이밖의 경우에는 감소효과를 인정할 수 없었다. 벼에서 전이계수의 감소 정도는 $^{85}Sr$가 60% 정도로 가장 컸고 배추와 무에서는 $^{54}Mn$가 80% 정도로 가장 컸다. 본 연구결과는 작물 생육중 농경지의 방사능 오염시 대책 수립을 위한 기초정보로 이용될 수 있다. The effects of a simultaneous application of KCl and lime on the root uptake of $^{54}Mn,\;^{60}Co,\;^{85}Sr\;and\;^{137}Cs$ by rice, soybean, Chinese cabbage and radish were investigated through 2 years' greenhouse experiments. At their early growth stages, a mixed solution of the radionuclides was applied to the water or soil surfaces of the culture boxes filled with an acidic loamy-sandy soil for the upper 20cm and $83g/m^2$ of fertilizer KCl and $200g/m^2$ of slake lime were applied to the surfaces. Distribution of radioactivities among plant parts and change in uptake pattern with plant species were not, on the whole, significantly affected by the application. It reduced effectively soil-to-plant transfer factors of $^{85}Sr\;and\;^{137}Cs$ for rice, of all for Chinese cabbage and of $^{54}Mn,\;^{60}Co,\;and\;^{137}Cs$ for radish without their growth inhibition. In rice, $^{85}Sr$ showed the highest decrease $({\sim}60%)$ while, in Chinese cabbage and radish, $^{54}Mn$ did $({\sim}80%)$. The exprimental results can become valuable reference data to establish countermeasures against a radioactive contamination of farm-land during plant growth.

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.

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.

첼렌코프광과 액체섬광계수법을 이용한 ⁸⁹Sr 및 ⁹⁰Sr 분석에 대한 연구

이명호,조영현,정근호,최근식,이창우,Lee, Myung-Ho,Chung, Geun-Ho,Cho, Young-Hyun,Choi, Geun-Sik,Lee, Chang-Woo 한국분석과학회 2002 분석과학 Vol.15 No.1

추출크로마토그래피와 액체섬광계수기를 이용하여 기존의 방사성 스트론튬 분석법 단점을 해결하는 신속하고 신뢰성 있는 $^{89}Sr$ 과 $^{90}Sr$ 분석법을 개발하였다. 옥살산 공침혹은 양이온 교환수지로 방해원소를 제거한 후 Sr-spec 컬럼을 사용하여 스트론튬만을 순수분리한 후, 액체섬광계수기를 사용하여 $^{89}Sr$에서 방출하는 첼렌코프광을 측정하였고 spectrum unfolding 방법으로 $^{90}Sr$을 정량하였다. 본 연구에서 개발된 방사성 스트론튬 분석법을 환경 표준시료 (IAEA-375, Soil) 및 액체 폐기물시료에 적용하여 분석법의 유효성을 검증하였다. An accurate and simple analytical technique for $^{89}Sr$ and $^{90}Sr$, overcoming the demerits of the conventional method, has been developed with extraction chromatography and liquid scintillation counting. The Sr fraction was separated from hindrance elements with oxalate coprecipitation or cation exchange resin and purified with Sr-Spec column. With liquid scintillation counter, $^{89}Sr$ was measured by Cerenkov radiation method, and $^{90}Sr$ was measured by spectrum unfolding method. The developed radioactive strontium separation method was validated by application to the IAEA-reference material (IAEA-375, Soil) and radioactive waste samples.

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.

원자력 시설 해체 폐기물 내 ⁵⁵Fe 와 ⁶³Ni 방사능 분석을 위한 전처리 방법 비교 연구

이훈,임종명,지영용,정근호,강문자,최근식,이진홍,Lee, Hoon,Lim, Jong-Myoung,Ji, Young-Yong,Jung, Kun-Ho,Kang, Mun-Ja,Choi, Geun-Sik,Lee, Jin-Hong 한국방사성폐기물학회 2015 방사성폐기물학회지 Vol.13 No.2

원자로의 해체 과정에서 발생되는 방사성 폐기물 내 존재하는 ⁵⁵Fe, ⁶³Ni은 폐기물의 처리방법을 결정하는 데 있어 기초적인 지표로 활용되는 중요한 핵종이다. 하지만 두 핵종은 낮은 방사선량으로 인해 다른 핵종들과의 분리가 필수적이며 또한 시료 매질에서 완전히 추출할 수 있는 전처리가 선행되어야 한다. 따라서 본 연구는 다양한 매질의 원자로 해체 폐기물에 대한 전처리방법의 적용성을 평가하기 위해 NIST SRM 5종 (1646a, 1944, 8704, 2709a, 1633c)에 대하여 왕수, 불산, 과염소산을 각각 이용하는 습식산화법과 alkali-fusion 전처리법에 따른 Iron와 Nickel의 회수율을 비교하였다. 실험 결과 alkali-fusion 방법은 다양한 매질의 인증표준물질에 대해 Iron 95.3∼98.3%, Nickle 86.6∼88.1%의 분석 정확도와 2% 이하의 정밀도를 나타냄으로서 해체폐기물 중 ⁵⁵Fe, ⁶³Ni, 분석에 가장 최적화된 전처리법으로 판단된다. ⁵⁵Fe and ⁶³Ni are key factors in deciding the proper handling of the decommissioning of radioactive waste from nuclear facilities. For determining beta emitting radionuclides, the dismantled waste samples should be completely decomposed and separated from the sample matrix. This study reports the comparison results of the recovering efficiencies of Iron and Nickel with wet digestion methods that use various acids and alkali-fusion methods. Various matrices of NIST SRMs (1646a, 1944, 8704, 2709a, and 1633c), the recovering efficiencies of using alkali-fusion methods ranged from 95.3 to 98.3% for Iron, and from 86.6 to 88.1% for Nickel within about 2% of relative standard deviation. On the other hand, those using one of the three wet digestion methods ranged from 77.9 to 105.3% for Iron and from 40.1 to 78.5% for Nickel with over 10% of relative standard deviation. Therefore, one may draw the conclusion that the analytical results derived from Iron and Nickel using alkali-fusion methods are fairly reliable due to the recovering efficiencies observed.

[화학]첼렌코프광과 액체섬광계수법을 이용한 ^(89)Sr 및 ^(90)Sr 분석에 대한 연구

이명호(Myung-Ho Lee),조영현(Geun-Ho Chung),정근호(Young-Hyun Cho),최근식(Geun-Sik Choi),이창우(Chang-Woo Lee) 한국분석과학회 2002 분석과학 Vol.15 No.1