• Journal of Korean Society for Atmospheric Environment
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• v.4 no.2
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• pp.1-10
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• 1988

Brookhaven 의학연구용 원자로에서 방출되는 기체분출물에 관하여 연구 되었다. 모든 기체시료는 $\gamma$-선 분광계측에 의하여 분석되었다. 시료 중에 존재하는 것으로 확인된 핵종으로서, $^{82}Cl(T_{1/2}$ = 35.30 시간) 이 가장 뚜렷하였다. 그 외의 확인된 핵종은 $^{38}Cl(T_{1/2}$ = 37.24분), $^{41}Ar(T_{1/2}$ = 1.82시간), $^{106}Rh(T_{1/2}$ = 29.80묘), $^{133}Te(T_{1/2}$ = 12.45분)이었다. 3MW 원자로 출력에서 pre-filter bank를 통과한 기체분출물 중에서 $$^{41}Ar$의 농도는 2.436Bq/cc로 계산됨으로써 $^{41}Ar$의 방사능 방출율은 8.51 ${\times}10^9$Bq/MW - h로 산정되었다. filter bank의 방사능 원거효율(%)은 $^{38}Cl$의 경우 97.84%, $^{41}Ar$은 14.15%, ^{82}Br$은 98.70% 그리고 $^{106}Rh$은 98.81% 각각 산정되었다. 한편, charcoal trap과 millipore filter 에서 확인된 기타 핵종들로서 $^{24}Na$, $^{72}Ga$, $^{92}Sr$, $^{97}Zr$, $^{132}I$, $^{133}Te$, $^{141}Ce$, $^{153}Sm$과 $^{154}Pm$은 filter bank에 의해서 완전히 제거되었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.806-811
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• 1995

DUPIC 핵연료주기에서 기준 핵연료로 설정된 사용후 경수로핵연료, 신 DUPIC 및 사용후 DUPIC핵연료의 핵종별 농도, 방사능, 붕괴열, 위해지수 및 방사선원항을 시간의 함수로 그 변화 특성을 분석하고, 각 인자별로 :-B게 영향을 미치는 주요 핵종의 거동을 물질농도 측면에서 추적하여 분석.평가 하였다. 방사성물질의 농도와 방사능 및 붕괴열 측면에서 모두 사용후 DUPIC핵 연료는 사용후 경수로핵연료에 111해 양적인 감소현상이 뚜렷하게 나타났다. 이는 DUPIC핵 연료주기의 경제적인 이득은 물론 환경 안전성 측면에서 크게 기여할 것임을 시사하고 있다. 한편 섭취 위해지수는 냉각기간에 따라 약간의 차이를 보이나 두 경우 비슷한 것으로 나타났으며, 방사선원 항의 세기에 있어서는 에너지 스펙트럼에 의존하는 것으로 나타났다. 이러한 결과는 향후 전체, DUPIC핵연료주기 평가에 있어서 기본 자료로 유용하게 활용될 수 있을 것으로 기대된다.

• Nuclear Engineering and Technology
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• v.27 no.2
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• pp.260-268
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• 1995

국내 원자력발전소의 방사성폐기물 발생량은 초고압 압축, 농축폐액 건조, 페수지 건조 등의 폐기물감용을 위한 운영계획이 수립되고 또한 일부 원자력발전소에서는 1995년부터 운영이 시작될 예정이어서 감소가 예상되고 있다. 원자력발전소로부터 방사성폐기물의 누적량은 2035년까지 운영자의 폐기물 감용 계획을 고려한다면 141,920 드럼으로 예상할 수 있고, 이에 상응하는 방사능량은 반감기가 한달 이상인 30개 핵종에 대하여 방사성 붕괴를 무시할 때 49,390 Ci였다. 특히 원자력환경관리센터에서 수행한 개념설계에 따른 1차 건설예정의 지하 처분동굴의 적재량인 약 10만 드럼은 2014년까지 누적량으로 채울 수 있고 이때 처분장의 장기적 성능평가에 주요 고려 대상인 반감기가 5년 이상의 14개 핵종에 대한누적 방사능량은 약 13,577 Ci였다. 이 예측된 발생량과 재고량은 처분장 장기적 성능 및 안전성 평가에 중요한 기초자료가 될 것이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.151-157
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• 2005

For the treatment of regulatory clearance of the soils, a procedure for the radionuclides and radioactivity concentration analysis is under development. A strategy for soil sampling including random sampling after homogenization and standardization was set up. Statistical representativeness is considered for not only sampling strategy but also sample size. In this study, designed sample size was designed with confidence interval and error bound of soil using the pilot samples which were taken following the sampling strategy.

• The Journal of the Korea Contents Association
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• v.14 no.6
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• pp.255-261
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• 2014

The generation amount of radioactive waste has been rapidly increased by increase of the usage of radioisotope source in medical field. Especially, the use of the radioactive source of I-131 with short half-life of 8.02 days used in treatment of thyroid has been increased, and all of the wastes concerned have been disposed by means of the self-disposal method. IAEA proposed criteria for clearance level of waste which depends on the individual (10 ${\mu}Sv/y$) and collective dose (1 man-Sv/y), and concentration of each nuclide (IAEA Safety Series No 111-P-1.1, 1992 and IAEA RS-G-1.7, 2004). In this study, various radioactive wastes in medical fields are collected and measured for establishing the disposal methods and procedures of radioactive wastes. In addition, comparison evaluation of decay storage period between the half-life which was calculated by attenuation curve based on real measurement and analytical half-life is considered. With comparing the theoretical half-life and the effective half life(7.72 days) which was based on the decay equation of measured data, it is resulted in the theoretical half-life is longer than effective half-life. The storage period of radioactive waste for self-disposal may be curtailed. The result of this study will be proposed as ISO standard.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.15 no.6
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• pp.3658-3666
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• 2014

The presence of $^{238}U$, $^{232}Th$ and $^{40}K$, which are naturally residing radionuclides, in the ordinary soil of Busan, the 2nd largest city in Korea, was anlayzed and the residents' radiation exposure to ordinary soil was evaluated. Regarding the measurement methods, to conduct a detailed analysis of the naturally residing radionuclides in the soil of Busan, this study divided the 16 administrative districts into a lattice structure with 3 spots, and collected a total of 48 soil samples (July 2012 and April 2013). ICP-MS was used to analyze the concentration of the radioactivity of $^{238}U$ and $^{232}Th$ in the soil, and a HpGe detector, a gamma ray detector, was used to analyze the radioactivity of $^{40}K$. The measurement values of this study were compared with the concentration of radioactivity of East Asian regions. The concentration of $^{238}U$ nuclides in Korea was lower than the mean, whereas the concentration of $^{232}Th$ and $^{40}K$ nuclides was higher than the mean. The higher mean concentrations of $^{232}Th$ and $^{40}K$ than the mean were attributed to the many granite areas that contain a great deal of naturally occurring radionuclides.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.2
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• pp.123-133
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• 2010

A statistical evaluation methodology was developed to determine the compliance of candidate waste stream with clearance criteria based upon distribution of radionuclide in a waste stream at a certain confidence level. For the cases where any information on the radionuclide distribution is not available, the relation between arithmetic mean of radioactivity concentration and its acceptable maximum standard deviation was demonstrated by applying widely-known Markov Inequality and One-side Chebyshev Inequality. The relations between arithmetic mean and its acceptable maximum standard deviation were newly derived for normally or lognormally distributed radionuclide in a waste stream, using probability density function, cumulative density function, and other statistical relations. The evaluation methodology was tested for a representative case at 95% of confidence level and 100 Bq/g of clearance level of radioactivity concentration, and then the acceptable range of standard deviation at a given arithmetic mean was quantitatively shown and compared, by varying the type of radionuclide distribution. Furthermore, it was statistically demonstrated that the allowable range of clearance can be expanded, even at the same confidence level, if information on the radionuclide distribution is available.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.3
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• pp.321-328
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• 2019

The detection performances of the NaI(Tl), $LaBr_3$(Ce) and $CeBr_3$ scintillation detectors, which can be used to rapidly evaluate the major artificial radionuclides deposited on the soil surface in a nuclear accident or radiological emergency, were compared. Detection performance was assessed by calculating the minimum detectable activity (MDA). The detection efficiency of each detector for artificial radionuclides was semi-empirically determined using mathematical modelling and point-like sources having certified radioactivity. The background gamma-ray energy spectrum for MDA evaluation was obtained from relatively wide and flat grassland, and the MDA values of each detector for the major artificial radionuclides that could be released in nuclear accidents were calculated. As a result, the relative MDA values of each detector regarding surface deposition distribution at normal environmental radiation level were evaluated as high in the order of the NaI(Tl), $LaBr_3$(Ce), and $CeBr_3$ detectors. These results were compared based on each detector's intrinsic and measurement environment background, detection efficiency, and energy resolution for the gamma-ray energy region of the radionuclide of interest.

• Journal of radiological science and technology
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• v.40 no.4
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• pp.633-638
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• 2017

The amount of radioactive waste has been rapidly increased with development of radiation treatment in medical field. Recently, it has been a common practice to use I-131 for thyroid cancer, F-18 for PET/CT and Tc-99m for diagnosis of nuclear medicine. All the wastes concerned have been disposed of by means of the self-disposal method, for example incineration, after storage enough to decay less than clearance level. IAEA proposed criteria for clearance level of waste which depends on the individual ($10{\mu}Sv/y$) and collective dose (1 man-Sv/y), and concentration of each nuclide (IAEA Safety Series No 111-P-1.1, 1992 and IAEA RS-G-1.7, 2004). In this study, specific radioactivity of radioactive waste contaminated with Re-186 was measured to confirm whether it meets the clearance level. Re-186 has long half life of 3.8 days relatively and emits beta and gamma radiation, therefore it can be applied in treatment and imaging purposes. The specific radioactivity of contaminated gloves weared by radiation workers was measured by MCA(Multi-channel Analyzer) which was calibrated by reference materials in accordance with the measuring procedure. As a result, comparison evaluation of decay storage period between the half-life which was calculated by attenuation curve based on real measurement and physical half-life was considered, and it is showed that the physical half-life is longer than induced half-life. Therefore, the storage period of radioactive waste for self-disposal may be curtailed in case of application of induced half-life. The result of this study will be proposed as ISO standard.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.363-364
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• 2008