• 한국환경과학회지
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• 제29권11호
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• pp.1089-1098
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• 2020

To assess the trophic function of an artificial macroalgal habitat, we compared the stable carbon and nitrogen isotope ratios of two amphipods (Caprella sp. and Ampithoe sp.) and their potential food sources in a transplanted macroalgal habitat (Grateloupia asiatica) with those in a natural habitat. There were no significant differences in the isotopic values of both consumers and their potential food sources between the transplanted and natural habitats. Such isotopic similarities between the two sites indicate a comparable resource consumer relationship. Additionally, our results showed similar isotopic niche areas and high dietary overlap (>65%) of the two amphipods between the transplanted and natural sites, suggesting that the transplanted habitat plays ecological roles similar to the natural habitat. Overall, isotopic assessment can provide information on the trophic function of diverse transplanted macroalgal habitats and improve post-monitoring efforts in the management of artificial ecosystems.

• 대한핵의학회지
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• 제19권2호
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• pp.5-16
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• 1985

• 자원환경지질
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• 제28권3호
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• pp.243-249
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• 1995

In order to investigate the origin of sulfate in rain waters and to evaluate the feasibility of using sulfur isotope method as a tracer of atmospheric pollutants, the sulfur isotopic ratio of sulfate in rain waters collected in Chonju city from October 1994 to March 1995 was monitored and was compared with those of possible sources proposed by previous works. The pH of rain waters shows an intermediate acidic range from 4.45 to 6.88 and their daily variation appears to be well correlated with to the amount of precipitation. The sulfur isotopic ratios of sulfate in rain waters show a highly restricted range from 0.0 to + 1.8‰. The ${\delta}^{34}S$ values are similar to those of soil and pine tree surrounding Chonju city, but largely deviate from those of China. D-parameter($d={\delta}D-8{\delta}^{18}O$) of rain waters varies from 9.4 to 28.8. The values indicate that the rain waters in Chonju city are originated from the rainy front of China continent. All data obtained from this study suggested that sulfate in the rain waters collected in Chonju city was mainly derived from the sulfur dioxide gas emitted by the petroleum combustion. Therefore, sulfur isotopic study for the precipitation provided an excellent tool for environmental assessment in this region and for tracing the source of atmospheric pollutants.

• 분석과학
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• 제31권3호
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• pp.134-142
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• 2018

The uranium isotopic ratio in environmental samples around nuclear facilities is important because it reveals information regarding illegal activities or anthropogenic pollution. Determination of uranium isotopes, however, is a challenging task requiring much labor and time because of the complex separation procedures and lengthy process. In this study, a rapid determination method for uranium isotopes in environmental samples was developed using. The sample was completely decomposed using the alkali fusion method. The separation procedure using extraction chromatography (UTEVA) was simplified in a single step without any further removal process for Si and major matrix elements. The established method can be completed within 3 h from sample dissolution to ICP-MS measurement. Most matrix elements and uranium isotopes in the soil samples were well separated and purified. Five types of were used to assess the method's accuracy and precision for a rapid uranium analysis method. The analytical accuracy for all CRM samples ranged from 95.1 % to 97.8 %, and the relative standard deviation was below 3.9 %. From the analytical results, one may draw conclusions that the evaluated method for uranium isotopes using alkali-fusion, the extraction chromatography process, and ICP-MS measurements is fast and fairly reliable owing to its recovering efficiencies. Thus, it is expected that the evaluated method can contribute to the improvement of environmental monitoring ability.

• 환경영향평가
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• 제27권6호
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• pp.685-694
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• 2018

본 연구에서는 저서성 대형무척추동물의 탄소와 질소 안정동위원소비를 이용하여 생태지위면적을 계산하고 수생태계 평가 활용 여부를 분석하였다. 평가를 위해 영산강 승촌보의 상류와 하류에 서식하고 있는 저서성 대형무척추동물의 생태지위면적을 6월과 8월 두차례에 걸쳐 비교하여 보로 인한 영향 유무를 집중호우 전후 시기로 구분하여 평가하였다. 또한, 수질과 군집지수 및 생물지수 (BMI)를 각각 측정하고 계산하여 계산된 생태지위면적과의 연관 관계를 알아보고자 하였다. 생태지위면적의 계산은 R 프로그램의 SIBER 패키지에서 제공하는 Bayesian Stable Isotope 기능을 이용하여 수행하였다. 승촌보 지역의 집중호우 이전 시기인 6월과 집중호우 이후 시기인 8월의 수질과 생물지수는 집중호우 전과 후 차이를 나타냈으나, 승촌보의 상류와 하류 지점에서 보로 인한 차이의 뚜렷한 경향은 나타나지 않았다. 반면, 저서성 대형무척추동물의 생태지위면적은 6월과 8월 조사에서 모두 상류 지역과 비교하여 하류 지역에서 감소하는 경향을 나타내었다. 이는 보로 인한 하천의 물리적 변화가 수질과 관계없이 저서성 대형무척추동물의 생태지위면적에 영향을 줄 수 있음을 의미하며, 종조성 변화와 같은 서식처 선호도에 따른 구성 생물의 변화와 같은 직접적인 영향 외에 서식처 환경 변화를 통한 종합적인 영향을 반영하는 것으로 판단된다. 따라서, 안정동위원소를 이용한 생태지위면적 값으로 먹이의 다양성, 선택성, 종의 생태적 지위, 경쟁 수준 등을 정량적으로 평가하여 기존의 지수를 이용한 평가방법을 보완할 수 있을 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제31권6호
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• pp.23-38
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• 1999

This study addresses the reference spent fuel and its characteristics for developing a geological repository concept. As a disposal capacity of the reference repository system to be developed, spent fuel inventories were projected based on the basis of the Nuclear Energy Plan of the Long-term National Power Program. The reference spent fuel encompassing a variability in characteristics of all existing and future spent fuels of interest was defined. Key parameters in the reference fuel screening processes were the nuclear and mechanical design parameters and the burnup histories for existing spent fuels as of 1996 and for future spent fuels with the more extended burnup the initial enrichment and its expected turnup. The selected reference fuel was characterized in terms of initial enrichment, bumup, dimension, gross weight and age. Also the isotopic composition and the radiological properties are quantitatively identified. This information provided in this study could be used as input for repository system development and performance assessment and applied in fuel material balance evaluation for the various types of back-end fuel cycle studies.

• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2415-2421
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• 2020

The axial heterogeneous void distribution in a fuel channel is a relevant and important issue during nuclear reactor analysis for LWR, especially for boiling water channel-type reactors. Variation of the coolant density in fuel channel has an effect on the neutron spectrum that will in turn have an impact on the values of absolute reactivity, the void reactivity coefficient, and the fuel isotopic compositions during irradiation. This effect is referring to as the history effect in light water reactor calculations. As the void reactivity effect is positive in RBMK type reactors, the underestimation of water density heterogeneity in 3D reactor core numerical calculations could cause an uncertainty during assessment of safe operation of nuclear reactor. Thus, this issue is analysed with different cross-section libraries which were generated with WIMS8 code at different reference water densities. The libraries were applied in single fuel model of the nodal code of QUABOX-CUBBOX/HYCA. The thermohydraulic part of HYCA allowed to simulate axial water distribution along fuel assembly model and to estimate water density history effect for RBMK type fuel.

• 분석과학
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• 제22권6호
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• pp.449-457
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• 2009

국내에 유통 중인 식품을 대상으로 PCBs 62종 동족체를 동위원소희석법으로 분석하고 노출평가를 실시하였다. 시료에 $^{13}C$-labeled된 회수율 측정용 표준용액을 가하여 추출하고 다층 칼럼 크로마토그래피로 정제하여 HRGC/MSD로 분석하였다. 식품 중 평균 검출량(ng/g)은 쌀 0.13, 육류 1.8~3.4, 우유 및 유가공품 0.3~3.7, 계란 10.0, 수산물 0.8~34.4 이었다. 식품군별 검출분포는 수산물(94.4%) >육류 (2.3%) >알류(1.7%) > 우유 및 유가공품(1.3%) >쌀(0.3%) 순이었다. 식품을 통한 총 PCBs의 1일 노출량은 14.5 ng/kg bw/day로 건강상 안전한 것으로 평가되었다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2009년도 학술논문요약집
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• pp.73-73
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• 2009

There are many factors to evaluate nuclear fuel cycle such as safety, public acceptance, economics, etc.. Transparency, proliferation, environment issues, public acceptance and safety are essential to expansion of nuclear industry and proliferation resistance is one of key constraints in the deployment of advanced nuclear energy systems. Proliferation resistance is being considered as one of the most important factors in assessing advanced and innovative nuclear systems. IAEA defmes proliferation resistance as characteristics of nuclear energy system that impedes the diversion or undeclared production of nuclear material [1]. Barriers to proliferation is consist of intrinsic and extrinsic barriers(institutional measures). Intrinsic barriers are characterized in material barriers and technical barriers in general. Material barriers is intrinsic, or inherent, qualities of materials that reduce the inherent desirability or attractiveness of the material as an explosive. Isotopic, chemical, radiological, mass and bulk, detectability barriers are considered as material barriers attributes [2]. Proliferation resistance is examined for several nuclear fuel cycles based on previous study which is focused on the intrinsic barriers [3-4]. Pyroprocessing and DUPIC are considered as reprocessing technologies in Korea and the PWR direct disposal is considered. Comparative assessments of the proliferation attributes and merits of different fuel cycle systems will be performed and the optimal back-end fuel cycle and strategy will be proposed.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.2830-2838
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• 2021

This work deals with the assessment of the burnup capabilities of the Serpent Monte Carlo code to predict spent nuclear fuel (SNF) isotopic concentrations for low-enriched uranium (LEU) fuel at different burnup levels up to 47 MWd/kgU. The irradiation of six UO₂ experimental samples in three different VVER-1000 reactor units has been simulated and the predicted concentrations of actinides up to ²⁴⁴Cm have been compared with the corresponding measured values. The results show a global good agreement between calculated and experimental concentrations, in several cases within the margins of the nuclear data uncertainties and in a few cases even within the reported experimental uncertainties. The differences in the performances of the JEFF3.1.1, ENDF/B-VII.1 and ENDF/B-VIII.0 nuclear data libraries (NDLs) have also been assessed and the use of the newly released ENDF/B-VIII.0 library has shown an increased accuracy in the prediction of the C/E's for some of the actinides considered, particularly for the plutonium isotopes. This work represents a step forward towards the validation of advanced simulation tools against post irradiation experimental data and the obtained results provide an evidence of the capabilities of the Serpent Monte-Carlo code with the associated modern NDLs to accurately compute SNF nuclide inventory concentrations for VVER-1000 type reactors.