• Asian Pacific Journal of Cancer Prevention
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• 제13권4호
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• pp.1693-1697
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• 2012

Objective: To explore the effect on radiosensitivity of arsenic trioxide ($As_20_3$) in conjunction with hyperthermia on the esophageal carcinoma EC-1 cell line. Method: Inhibition of EC-1 cell proliferation at different concentrations of $As_20_3$ was assessed using the methyl thiazolyl blue colorimetric method (MTT method), with calculation of $IC_{50}$ value and choice of 20% of the $IC_{50}$ as the experimental drug concentration. Blank control, $As_20_3$, hyperthermia, radiotherapy group, $As_20_3$ + hyperthermia, $As_20_3$ + radiotherapy, hyperthermia + radiotherapy and $As_20_3$ + hyperthermia + radiotherapy groups were established, and the cell survival fraction (SF) was calculated from flat panel colony forming analysis, and fitted by the 'multitarget click mathematical model'. Flow cytometry (FCM) was used to detect changes in cell apoptosis and the cell cycle. Results: $As_20_3$ exerted inhibitory effects on proliferation of esophageal carcinoma EC-1 cells, with an $IC_{50}$ of 18.7 ${\mu}mol/L$. After joint therapy of $As_20_3$ + hyperthermia + radiotherapy, the results of FCM showed that cells could be arrested in the $G_2$/M phase, and as the ratio of cells in $G_0/G_1$ and S phases decreased, cell death became more pronounced. Conclusion: $As_20_3$ and hyperthermia exert radiosensitivity effects on esophageal carcinoma EC-1 cells, with synergy in combination. Mechanistically, $As_20_3$ and hyperthermia mainly influence the cell cycle distribution of EC-1 esophageal carcinoma cells, decreasing the repair of sublethal damage and inducing apoptosis, thereby enhancing the killing effects of radioactive rays.

• 한국수산과학회지
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• 제16권4호
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• pp.379-388
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• 1983

본 조사는 전남 여천군 돌산읍 죽포리 두문포의 조하대 해조군락의 특성을 밝히기 위하여 1982년 6월 부터 1983년 5월 까지 연간 계절별로 SCUBA 잠수에 의해 채집된 자료를 분석하므로 수행되었다. 조하대의 수직분포는 sheltered 지역의 특성을 나타내고 있고, 상부, 중부, 하부의 3개 구역으로 나누어지며, 상부는 Ulva pertusa, Codium fragile, Chondria crassicaulis, Gigartina tenera의 녹조, 홍조류, 중부는 Myagropsis myagroides와 Sargassum tortile의 대형갈조류, 하부는 Plocamium telfairiae, Callophyllis japonica, Symphyocladia linearis의 홍조류가 우점종으로 나타났다. Normal association analysis를 통한 군락분석결과 이 지역 해조군락은 9개의 group으로 나누어지고, 각 group의 우점종은 각각 Sargassum tortile, Myagropsis myagroides, Chondrin crassicaulis, Codium fragile, Pterocladia tenuis, Gigartina tenera, Gracilaria textorii등이었고 이 지역의 해중림을 조성하는 대표적 종은 Myagropsis myagroides와 Sargassum tortile 이었다. 한편, Myagropsis myagroides의 현존량은 $50{\times}50cm$당 봄철에 5,248g, 여름에는 650.4g, 가을에는747.6g이었고, 평균체장은 봄부터 가을까지 계절별로 각각 169.9cm, 48,4cm, 149.9cm여서 생식이 끝난 직후인 봄철에 최고치를 나타내고 소멸기인 여름에 최소치를 나타냈다.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.378-383
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• 2016

Background: Radiation dose rates in PRIDE facility is evaluated quantitatively for assessing radiation safety of workers because of large amounts of depleted uranium being handled in PRIDE facility. Even if direct radiation from depleted uranium is very low and will not expose a worker to significant amounts of external radiation. Materials and Methods: ORIGEN-ARP code was used for calculating the neutron and gamma source term being generated from depleted uranium (DU), and the MCNP5 code was used for calculating the neutron and gamma fluxes and dose rates. Results and Discussion: The neutron and gamma fluxes and dose rates due to DU on spherical surface of 30 cm radius were calculated with the variation of DU mass and density. In this calculation, an imaginary case in which DU density is zero was added to check the self-shielding effect of DU. In this case, the DU sphere was modeled as a point. In case of DU mixed with molten salt of 50-250 g, the neutron and gamma fluxes were calculated respectively. It was found that the molten salt contents in DU had little effect on the neutron and the gamma fluxes. The neutron and the gamma fluxes, under the respective conditions of 1 and 5 kg mass of DU, and 5 and $19.1g{\cdot}cm^{-3}$ density of DU, were calculated with the molten salt (LiCl+KCl) of 50 g fixed, and compared with the source term. As the results, similar tendency was found in neutron and gamma fluxes with the variation of DU mass and density when compared with source spectra, except their magnitudes. Conclusion: In the case of the DU mass over 5 kg, the dose rate was shown to be higher than the environmental dose rate. From these results, it is concluded that if a worker would do an experiment with DU having over 5 kg of mass, the worker should be careful in order not to be exposed to the radiation.

• 동력기계공학회지
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• 제13권3호
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• pp.40-46
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• 2009

This study on the bolt elongation and torque measuring method by ultrasonic nod-destructive method. In the past, The dial gage was used for the elongation measurement of gas turbine bolts. The purpose of this study is to improve the traditional bolt elongation measurement method. The old method using dial gage measures the elongation of the gas turbine bolt. If the length differences among the loading bolts are within the required range, The loading torques of bolts consider as acceptable. But this method can not give the information about torque differences among the loading bolts. It could bring out vibration of turbine due to loading torque differences among the bolts. So the elongation and torque must be measured simultaneously. The new technology using ultrasonic non-destructive method can give the information about bolt elongation and torque. The ultrasonic method basically measures the speed in the bolt material for the calculation the bolt elongation. But the ultrasonic speed varies according to temperature and loading torque of bolts. So the factors of temperature and loading power were investigated and reflected to the calculation of bolt elongation and torque. The results of this study shows the big difference among the bolts torque in the old method and the torque differences among the bolts can be adjusted by reflecting the result of this study. And this torque adjusting method can decrease gas turbine vibration problem due to torque difference among the bolts. So this paper shows ultrasonic method is better than old method for the measurement of bolt elongation and torque.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3732-3753
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• 2023

The Real-time Analysis for Particle-transport and In-situ Detection (RAPID) Code System, developed based on the Multi-stage Response-function Transport (MRT) methodology, enables real-time simulation of nuclear systems such as reactor cores, spent nuclear fuel pools and casks, and sub-critical facilities. This paper presents the application of a novel fission matrix-based burnup methodology to the well-characterized JSI TRIGA Mark II research reactor. This methodology allows for calculation of nuclear fuel depletion by combination and interpolation of RAPID's burnup dependent fission matrix (FM) coefficients to take into account core changes due to burnup. The methodology is compared to experimentally validated Serpent-2 Monte Carlo depletion calculations. The results show that the burnup methodology for RAPID (bRAPID) implemented into RAPID is capable of accurately calculating the k_eff burnup changes of the reactor core as the average discrepancies throughout the whole burnup interval are 37 pcm. Furthermore, capability of accurately describing 3D fission source distribution changes with burnup is demonstrated by having less than 1% relative discrepancies compared to Serpent-2. Good agreement is observed for axially and pin-wise dependent fuel burnup and nuclear fuel nuclide composition as a function of burnup. It is demonstrated that bRAPID accurately describes burnup in areas with high gradients of neutron flux (e.g. vicinity of control rods). Observed discrepancies for some isotopes are explained by analyzing the neutron spectrum. This paper presents a powerful depletion calculation tool that is capable of characterization of spent nuclear fuel on the fly while the reactor is in operation.

• Korean Chemical Engineering Research
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• 제61권2호
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• pp.258-264
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• 2023

지속가능한 바이오에너지 이용을 위해서는 국내 바이오매스 이용 확대와 지속가능성 증대가 필수적인데, 국내 관련 체계는 아직 미비한 상황이다. 이에 바이오 연료에 대한 지속가능성 평가를 위한 앞선 체계가 마련되어 있는 EU의 RED-II 방법론을 활용하여 국내 농업 잔재물 바이오매스인 케나프(Hibiscus cannabinus L.) 줄기 펠릿을 이용한 바이오매스 발전의 전과정 온실가스 배출량을 이론적으로 산정하였다. 케나프 잔재물 펠릿의 생산경로에 대해 EU 공동연구센터(Joint Research Center)의 배출계수를 이용하여 잔재물 수집, 운송, 펠릿 연료화까지의 전과정 온실가스 배출량을 산정한 결과, 배출량은 3.0 gCO₂eq/MJ로 나타났고 이를 25% 발전효율로 연소하여 전력을 생산하는 경우 전과정 온실가스 배출량은 11.9 gCO₂eq/MJ로 산출되었다. 이는 전력배출계수로 환산하면 42.8 kgCO₂eq/MWh로, 국내 전력배출계수 443.4 kgCO₂eq/MWh와 비교하면 90.3%의 온실가스 배출량 감축을 달성할 수 있는 것으로 분석되었다. 또한 수입 목재펠릿과 비교하는 경우 최소 59.6%의 온실가스 배출 감축이 가능하여, 국내 발생 잔재물 바이오매스를 바이오에너지 생산에 이용하는 경우 기존 수입 목재펠릿에 비하여 높은 수준의 온실가스 배출 감축 달성이 가능함을 확인하였다. 이는 국내 바이오에너지의 전과정온실가스 배출량평가 체계 마련을위한 기초자료로 활용될 수있을 것으로기대된다.

• 대한방사선치료학회지
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• 제17권2호
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• pp.87-94
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• 2005

목 적 : 공작실에서 block을 제작할 때 중금속이 사용된다. 이때 발생하는 중금속 분진 및 발연(發煙)은 인체에 위해를 준다. 이러한 중금속의 측정과 분석을 통해 심각성을 인식한다. 또한 그에 따른 해결방안을 강구하는 것이 논문의 목적이다. 대상 및 방법 : 논문에 사용되는 기구는 유도 결합 플라즈마 방출분광기이며, 대전 시내 4개 대학병원 방사선 종양학과 공작실(비스무스, 납, 주석, 카드뮴)을 대상으로 하였다. 실험방법은 ppb 단위로 포집하여 비교 분석하고, 체내 및 혈중 중금속 기준치를 통한 공기 중 중금속의 기준치를 계산하며 중금속 임시 기준치를 설정하였다. 결 과 : 지하생활공간 공기 질 관리법에서 정해진 납과 카드뮴의 기준치(24시간 기준)는 $3{\mu}g/m^3$과 $2{\mu}g/m^3$이다. 그리고 비스무스와 주석은 체내 및 혈중 기준치와 다른 중금속 기준치를 통해 $7{\mu}g/m^3$과 $6{\mu}g/m^3$로 정하였다. 대전지역 4개 대학병원 공작실 내부 중금속 측정치를 작업 유무에 따라 비교한다. 비작업 시에는 측정치 대부분이 기준치 이하로 나왔다. 하지만 작업을 하고 있을 경우에는 높은 수치를 나타났다. 또한 차폐체의 구성 비율에 따른 검출 비율의 연관성도 보였다. 결 론 : 작업종사자의 중금속 오염 심각성에 대한 해결방법은 근본적인 부분에서 찾아야 한다. 병원에서는 국소 배기장치의 설치 및 주기적 성능 점검, 보호구 제공 등이 시행되어져야 한다. 또한 작업자는 지속적인 관심과 위생관리, 중금속 오염에 대한 부분을 인식해야 한다. 마지막으로 학회 차원에서 기준치 설정 및 주기적인 측정을 통해 지속적으로 관리를 해야 한다. 그리고 정기적인 특수건강진단의 실시와 같은 근본적인 해결방안을 찾아야겠다.

• Asian-Australasian Journal of Animal Sciences
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• 제27권1호
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• pp.69-76
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• 2014

This study was carried out to evaluate the relationship between threonine (Thr) efficiency and Thr dehydrogenase (TDG) activity as an indicator of Thr oxidation on chicks fed with levels of diets (CP [17.5% and 21.5%] and Thr [3.8 and 4.7 g/100 g CP]; glycine [Gly][0.64% and 0.98%] and true digestible Thr [dThr] [0.45% and 0.60%]). Calculation of the Thr efficiency was based on N-balance data and an exponential N-utilization model, and TDG activity was determined as accumulation of aminoacetone and Gly during incubation of hepatic mitochondria. This study found that in the liver of chicks who received a diet containing up to 0.79% Thr (4.7 g Thr/100 g of CP) in the 17.5% CP diet, no significant (p>0.05) effect on TDG activity was observed. However, significantly (p = 0.014) increased TDG activity was observed with a diet containing 21.5% CP (4.7 g Thr/100 g of CP) and the efficiency of Thr utilization showed a significant (p = 0.001) decrease, indicating the end of the Thr limiting range. No significant (p>0.05) effect on the total TDG activity and accumulation of Gly was observed with addition of Gly to a diet containing 0.45% dThr. In addition, addition of Gly to a diet containing 0.60% dThr also did not result in a change in accumulation of Gly. Due to an increase in accumulation of aminoacetone, an elevated effect on total TDG activity was also observed. No significant (p>0.05) reduction in the efficiency of Thr utilization was observed after addition of Gly at the level of 0.45% dThr. However, significantly (p<0.001) reduced efficiency of Thr utilization was observed after addition of Gly at the level of 0.60% dThr. Collectively, we found that TDG was stimulated not only by addition of Thr and protein to the diet, but also by addition of Gly, and efficiency of Thr utilization was favorably affected by addition of Gly at the level near to the optimal Thr concentration. In addition, no metabolic requirement of Gly through the TDG pathway was observed with almost the same accumulation of Gly and a slight increase in TDG activity by addition of Gly. Thus, our findings suggest that determination of TDG activity and parameter of efficiency of Thr utilization may be useful for evaluation of dietary Thr level.

• 한국전산유체공학회지
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• 제20권3호
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• pp.1-7
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• 2015

When the steam is used as working fluid in fluid machinery, different from other gases as air, phase transition (steam condensation) can occur and it affects not only the flow fields, but also machine performance & efficiency. Therefore, considering phase transition phenomena in CFD calculation is required to achieve accurate prediction of steam flow and non-equilibrium wet-steam model is needed to simulate realistic steam condensing flow. In this research, non-equilibrium wet-steam model is implemented on in-house code(T-Flow), the flow fields including phase transition phenomena in convergent-divergent nozzle are studied and compared to results of advance researches.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.207-214
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• 2001

The KN-12 spent nuclear fuel (SNF) transport cask is designed for transportation of up to 12 assemblies and is in standby status for being licensed in accordance with Korea Atomic Energy Act. To evaluate radiation shielding and criticality safety of the KN-12 cask, each case of study was carried out using MCNP4B Code. MCNP code is verified by performing benchmark calculation for the KSC-4 SNF cask designed in 1989. As a result of radiation safety evaluation for the KN-12 cask, calculated dose rates always satisfied the standards at the cask surface, at 2m from the surface in normal transport condition, and at 1 m from the surface in hypothetical accident condition. Maximum dose rate was always arisen on the side of the cask. For normal transport condition, photons primarily contribute to dose rate between two kinds of released sources, neutrons and photons, from spent nuclear fuel but for hypothetical accident condition, contrary case was resulted. The level of calculated dose rate was 27.8% of the limit at the cask surface, 89.3% at 2 m from the cask surface, and 25.1% at 1 m from the cask surface. For criticality analysis, keff resulting from the criticality analysis considering the condition of optimum partial flooding with fresh water is 0.89708(0.00065. The results confirm the standards recommended by all regulations on radiation safety.