• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.39-40
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• 2009

2009년 4월 29일 신월성원전 건설현장에 해수가 유입되어 건설 중에 있던 구조물과 건축 재료가 해수에 침수되는 사고가 발생하였다. 이 후 지역의 대표들이 신월성침수사고 조사위원회를 구성하여 침수된 구조물의 안전성과 보수가 필요한 부분을 정량적으로 평가하고 그 결과를 발표하였다. 본 논문에서는 침수사고의 개요와 조사위원회의 구성과정 및 활동 그리고 조사위원회의 의미 등을 살펴보고 이 때 월성원전감시기구의 역할 등을 고찰하여 원전주변지역 주민의 의식변화와 이에 따른 관련기관의 역할을 기술하였다.

• 한국해양학회지
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• v.4 no.1
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• pp.9-16
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• 1969

The sand drift movement at Young Il Bay area was tentatively investigated using Co-60 glass sand. Grain size and specific gravity of the glass sand which has originally contained natural cobalt, Co-59, was made similar to those of the real coastal sand, and was irradiated in a beam port of the reactor Triga Mark II to make the glass sand radioactive by the reaction of 59Co(n, r)60Co. The radioactive cobalt glass sand was deposited on the preselected point of sea bed, and, after a couple of weeks, the drift of sand was traced by means of specially designed water-proof G-M detector. Net counts at each point were plotted to figure out equicount lines and consequently such aspects as the direction of sand drift movement, the scope of distribution and the relative drift velocity etc. were indicated.

• The Journal of the Korea Contents Association
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• v.5 no.5
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• pp.281-286
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• 2005

This research is to measure the irradiation dose in radiological technologists with 623 radiological technologists working at 44 general hospitals in 16 cities and states nation-wide, during one month from July to August 2003. Questionnaires were used to analyze the dose, while existing data from measurements taken in 5 years was used to analyze amounts of radiation dose level. Average annual irradiation dose level was $1.73{\pm}0.10mSv$ in 5 years from 1998 to 2002. Annually, 2000 had the highest level With $1.80{\pm}0.15mSv$, While 1998 was lowest with $1.36{\pm}0.12mSv$, but a long-term solution needs to be worked out since there is a possibility of chronic exposure due to the nature of the work. The results of present research shows that the radiological technologists are effecting managing irradiation dose.

• Journal of Radiation Protection and Research
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• v.17 no.2
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• pp.49-59
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• 1992

A new model was developed in order to investigate the effects of chelating agents on the migration of a radionuclide in the form of ion or chelate. The migration behavior of the chelated radionuclide was analyzed by formulating a convective-dispersion transport equation which included a degradation of chelating agent and chelated radionuclide. The mathematical model was analytically solved and checked with the existing retardation factor. The results show that the migration velocity of the chelated radionuclide was much faster than the ionic one due to the decreased retardation. Therefore, it was concluded that a new remedial action should be developed to reduce the generation and release of chelating agents from the nuclear power plant into the environment.

• Nuclear Medicine and Molecular Imaging
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• v.40 no.4
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• pp.228-232
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• 2006

Purpose: electrophilic $^{18}F(T_{1/2}=110\;min)$ radionuclide in the form of $[^{18}F]F_2$ gas is of great significance for labeling radiopharmaceuticals for positron omission tomography (PET). However, its production In high yield and with high specific radioactivity is still a challenge to overcome several problems on targetry. The aim of the present study was to develop a method suitable for the routine production of $[^{18}F]F_2$ for the electrophilic substitution reaction. Materials and Methods: The target was designed water-cooled aluminum target chamber system with a conical bore shape. Production of the elemental fluorine was carried out via the $^{18}O(p,n)^{18}F$ reaction using a two-step irradiation protocol. In the first irradiation, the target filled with highly enriched $^{18}O_2$ was irradiated with protons for $^{18}F$ production, which were adsorbed on the inner surface of target body. In the second irradiation, the mixed gas ($1%[^{19}F]F_2/Ar$) was leaded into the target chamber, fellowing a short irradiation of proton for isotopic exchange between the carrier-fluorine and the radiofluorine absorbed in the target chamber. Optimization of production was performed as the function of irradiation time, the beam current and $^{18}O_2$ loading pressure. Results: Production runs was performed under the following optimum conditions: The 1st irradiation for the nuclear reaction (15.0 bar of 97% enriched $^{18}O_2$, 13.2 MeV protons, 30 ${\mu}A$, 60-90 min irradiation), the recovery of enriched oxygen via cryogenic pumping; The 2nd irradiation for the recovery of absorbed radiofluorine (12.0 bar of 1% $[^{19}F]fluorine/argon$ gas, 13.2 MeV protons, 30 ${\mu}A$, 20-30 min irradiation) the recovery of $[^{18}F]fluorine$ for synthesis. The yield of $[^{18}F]fluorine$ at EOB (end of bombardment) was achieved around $34{\pm}6.0$ GBq (n>10). Conclusion: The production of $^{18}F$ electrophilic agent via $^{18}O(p,n)^{18}F$ reaction was much under investigation. Especially, an aluminum gas target was very advantageous for routine production of $[^{18}F]fluorine$. These results suggest the possibility to use $[^{18}F]F_2$ gas as a electrophilic substitution agent.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.571-576
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• 1998

방사성물질의 수송용기 등에 사용되는 에폭시수지계 중성자 차폐재를 제조하였다 기본물질은 재질(KNS-102) 및 수소 첨가된 비스페놀 A힘(KNS-106) 그리고 패놀-노블락형 에폭시수지 (KNS-611)이며, 첨가제로는 수산화알루미늄 및 탄화붕소이다. 이들 중성자 차폐재들은 유동성이 좋아 수송용기와 같은 복잡한 구조에 사용할 수 있다. 제조된 중성자 차폐재들을 방사선 조사선 량에 대한 영향과 가압경수로 사용후핵연료_ 28다발을 수송할 수 있는 수송용기에 적용하여 차폐능 평가를 수행하였다 0.7 MGy 까지 중성자 차폐재들은 방사선 조사선량의 증가에 따라 중성자 차폐재의 거시적 제거 단면적($\Sigma$$_{R}$)은 약간 증가하는 경향을 나타내었으며, 수송용기에 적용하여 ANISN 전산코드로 차폐능 평가를 수행한 결과 정상수송시 중성자 차폐재의 두께가 12 cm 이상일 때 수송용기 반경방향표면에서 최대 방사선량율은 168 ~ 214 $\mu$Sv/h로 나타났으며, 수송용기 표면에서 100 cm 지점에서의 최대 방사선량율은 74 ~ 93 $\mu$Sv/h로 나타났다. 이들은 모두 관련된 법규들에서 규정된 최대 허용방사선량율을 만족하는 것으로 나타났다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.96-100
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• 2003

Filtering system is installed at post irradiation examination facility(PIEF) to maintain optimized operating condition of the facility by keeping different negative pressure condition depending on contamination level in the PIEF due to its treatment of radioactive materials. Inspection on each system, filter leak test and other related test are periodically performed as the performance test for increasing operational efficiency and safety.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.133-134
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• 2009

조사 핵연료 및 구조재료의 핫셀시험을 위한 조사재시험시설은 고방사능물질의 시험 및 취급과정에서 발생한 각종 방사성 물질에 오염된 공기를 정회하기 위한 특수 공기조화설비를 운영하고 있다. 시설의 배기 계통은 핫셀 계통 및 핫셀 이외의 계통으로 니눠지고 있다. 그 중 핫셀 구역 이외의 공기는 1차적으로 프리필터와 HEPA 필터로 구성된 AFU(Air Filtering Unit)로 정화하여 외부에 방출하는 MUP(Medium Under Pressure) 시스템을 채용하고 있다. 외부에 방출하는 배기의 오염을 최소화하기 위하여 설치된 AFU에 대한 풍량 측정 및 HEPA필터의 성능시험을 실시하였으며, 그 결과에 대하여 고찰하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.24-31
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• 2004

In order to decommission safely nuclear power plant, it is necessary for the procedure of residual radioactivity investigation in site to provide detailed guidance for planning, implementing, and evaluating environmental and facility radiological surveys conducted to demonstrate compliance with a dose or risk-based regulation. This study presents the procedure of residual radioactivity investigation in decommissioning site - Historical Site Assessment, Scoping Survey, characterization Survey, Remedial Action Support Survey, Final Status Survey - on the basis of MARSSIM(Multi-Agency Radiation Survey and Site Investigation Manual) and investigation cases of decommissioned or decommissioning nuclear power plant.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.763-768
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• 1998

방사성동위원소 생산용 표적을 중성자 조사하기 위해 하나로의 제반 특성을 고려하여 조사용기를 개발하였다 IP(Isotope Production), HTS(Hydraulic Transfer System) 조사공별로 내.외부용기를 제작하였으며 재료는 검증된 Al-1050을 사용하였다. 내부용기는 냉간용접(Cold Welding) 하고, 외부용기는 TIG(Tungsten Inert Gas) 또는 전자빔으로 용접한 후 He을 충진하고 밀봉하였다. 조사용기의 건전성을 입증하기 위해 기포누설시험, 내압시험, 가열시험, 침투탐상시험, He 누설시험을 수행하였다. 기포누설시험 결과 내부용기는 90% 이상이 3x$10^{-6}$atm.cc/sec 이하의 누설율을 보였고, 내압시험 결과 파단압력은 28kg/$\textrm{cm}^2$ 정도였다. 외부용기는 TIG 용접시 70%, 전자빔 용접시 90% 이상이 누설율 1x$10^{-8}$atm.cc/sec 이하였다. 개발된 조사용기를 사용하여 하나로에서 200여회 방사성동위원소를 생산하였으나 중성자 조사중 누출을 포함한 기타의 문제가 발생하지 않았다. 조사용기 개발에서 확립된 밀봉시험, 내압시험 및 가열시험 방법은 기체표적이나 내압이 발생하는 표적용기의 개발 및 시험에 응용할 수 있다.