• Nuclear Engineering and Technology
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• 제37권6호
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• pp.537-556
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• 2005

A primary-pipe rupture accident is one of the design-basis accidents of a High-Temperature Gas-cooled Reactor (HTGR). When the primary-pipe rupture accident occurs, air is expected to enter the reactor core from the breach and oxidize in-core graphite structures. This paper describes an experiment and analysis of the air ingress phenomena and the method fur the prevention of air ingress into the reactor during the primary-pipe rupture accident. The numerical results are in good agreement with the experimental ones regarding the density of the gas mixture, the concentration of each gas species produced by the graphite oxidation reaction and the onset time of the natural circulation of air. A hydrogen production system connected to the High-Temperature Engineering Test Reactor (HTTR) Is being designed to be able to produce hydrogen by themo-chemical iodine-Sulfur process, using a nuclear heat of 10 MW supplied by the HTTR. The HTTR hydrogen production system is first connected to a nuclear reactor in the world; hence a permeation test of hydrogen isotopes through heat exchanger is carried out to obtain detailed data for safety review and development of analytical codes. This paper also describes an overview of the hydrogen permeation test and permeability of hydrogen and deuterium of Hastelloy XR.

• 한국환경과학회지
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• 제11권10호
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• pp.1097-1101
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• 2002

Activated carbon is amorphous and its intraparticle pores are well developed. Thus it has high adsorption capabilities and catalytic effect, and is utilized in many areas of industries such as food processing. In recent years, the demand of activated carbon has been increased to solve the environmental problems-waste treatment and removal of poisonous gas. Therefore, in this study an activated carbon was made using the waste and then the industrial characteristics of the produced activated carbon were investigated. The result showed that the carbonization yield was decreased when carbonization temperature was increased from 400 to $600^{\circ}C$ and that the optimal carbonization temperature was $500^{\circ}C$. The optimal concentration of NaOH for removing ash in the raw sample was 1~2N. The iodine adsorption of activated carbon using waste sample at $500^{\circ}C$ carbonization was 1204.28mg/g. The activation result of carbonization sample showed that the optimal activation condition was the carbonization at $500^{\circ}C$ and the activation at $800^{\circ}C$. So the production of activated carbon was thought to be possible, reused as resource, and decreased the environmental pollution.

• Korean Journal of Radiology
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• 제21권7호
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• pp.838-850
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• 2020

Computed tomography (CT) is an important imaging modality in evaluating thoracic malignancies. The clinical utility of dual-energy spectral computed tomography (DESCT) has recently been realized. DESCT allows for virtual monoenergetic or monochromatic imaging, virtual non-contrast or unenhanced imaging, iodine concentration measurement, and effective atomic number (Z_eff map). The application of information gained using this technique in the field of thoracic oncology is important, and therefore many studies have been conducted to explore the use of DESCT in the evaluation and management of thoracic malignancies. Here we summarize and review recent DESCT studies on clinical applications related to thoracic oncology.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1099-1109
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• 2020

The performance of gadolinium burnable absorber (GdBA) for reactivity control in UO₂ and (U, Th)O₂ fuels and its impact on spent fuel characteristics was performed. Five fuel assemblies: one without GdBA fuel rod and four each containing 16, 24, 34 and 44 GdBA fuel rods in both fuels were investigated. Reactivity swing in all the FAs with GdBA rods in UO₂ fuel was higher than their counterparts with similar GdBA fuel rods in (U, Th)O₂ fuel. The excess reactivity in all FAs with (U, Th)O₂ fuel was higher than UO₂ fuel. At the end of single discharge burn-up (~ 49.64 GWd/tHM), the excess reactivity of (U, Th) O₂ fuel remained positive (16,000 pcm) while UO₂ fuel shows a negative value (-6,000 pcm), which suggest a longer discharge burn-up in (U, Th)O₂ fuel. The concentration of plutonium isotopes and minor actinides were significantly higher in UO₂ fuel than in (U, Th)O₂ fuel except for ²³⁶Np. However, the concentration of non-actinides (gadolinium and iodine isotopes) except for ¹³⁵Xe were respectively smaller in (U, Th)O₂ fuel than in UO₂ fuel but may be two times higher in (U, Th)O₂ fuel due to its potential longer discharge burn-up.

• 한국식품조리과학회지
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• 제8권2호
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• pp.95-105
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• 1992

This study was carried on the Seasoning Oil production by Autoclaving Method in order to research a developed method. The Raw, Extract states of seasoning vegetables-Garlic, Onion and Ginger were added 40, 60% (w/w) of total amounts to corn salad oil. All samples treated with various conditions were determined physicochemical characteristics by Acid value, Peroxide value, Iodine value, Refractive Index, and Volatile Carbonyl Compound Content during incubating $(40{\pm}2^{\circ}C)$ and heating $(185{\pm}2^{\circ}C)$. The results were obtained as follws; 1. During incubation at $40{\pm}2^{\circ}C$, the order of antioxidative effects among seasoning vegetables was Ginger>Garlic>BHA>Onion and Extract state were more effective man Raw state. also the antioxidative effects of the seasoning vegetables were increased proportionally with the concentration in the Seasoning Oils. 2. In the case of heat treatment $(185{\pm}2^{\circ}C)$, AV, POV, IV and RI of each Seasoning Oil were changed very sharply. The antioxidative effect and Carbonyl Compound Content according to heat treatment differed from the type and concentration of seasoning vegetables in oil. Ginger had the most excellent antioxidative effect among seasoning vegetables, and m any case, the adding states of seasoning vegetables into oils were more effective in Extract man Raw states. 3. According to those results, each Seasoning Oil made from Garlic, Onion, Ginger was shown to have antioxidative properties specially in Ginger-Extract-Seasoning Oil. also the Autoclaving Method was thought to be rational method in preparation of Seasoning Oil.

• Nuclear Engineering and Technology
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• 제44권4호
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• pp.369-378
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• 2012

A load-following operation in APR+ nuclear plants is necessary to reduce the need to adjust the boric acid concentration and to efficiently control the control rods for flexible operation. In particular, a disproportion in the axial flux distribution, which is normally caused by a load-following operation in a reactor core, causes xenon oscillation because the absorption cross-section of xenon is extremely large and its effects in a reactor are delayed by the iodine precursor. A model predictive control (MPC) method was used to design an automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control for APR+ nuclear plants. Some tracking controllers employ the current tracking command only. On the other hand, the MPC can achieve better tracking performance because it considers future commands in addition to the current tracking command. The basic concept of the MPC is to solve an optimization problem for generating finite future control inputs at the current time and to implement as the current control input only the first control input among the solutions of the finite time steps. At the next time step, the procedure to solve the optimization problem is then repeated. The support vector regression (SVR) model that is used widely for function approximation problems is used to predict the future outputs based on previous inputs and outputs. In addition, a genetic algorithm is employed to minimize the objective function of a MPC control algorithm with multiple constraints. The power level and ASI are controlled by regulating the control banks and part-strength control banks together with an automatic adjustment of the boric acid concentration. The 3-dimensional MASTER code, which models APR+ nuclear plants, is interfaced to the proposed controller to confirm the performance of the controlling reactor power level and ASI. Numerical simulations showed that the proposed controller exhibits very fast tracking responses.

• Applied Biological Chemistry
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• 제51권3호
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• pp.153-158
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• 2008

토양으로부터 tyrosinase 저해제를 생산하는 방선균 F-97을 분리하여, 이 균이 생산하는 tyrosinase 저해제를 정제하였다. 먼저 배양액을 원심분리하고 이 여액을 pH 4.0으로 조절한 후 IRC-120($NH_4^+$ type column chromatography, Silica gel column chromatography, C18 column chromatography, Sephadex LH-20 column chromatography를 사용하여 정제하였다. 정제도 확인은 ODS HPLC를 이용하여 확인하였으며, 최종 정제 수율은 5.24%이었다. 물리 화학적 특성으로 tyrosinase 저해제는 water, methanol, ethanol 등에는 잘 녹았으나, acetone, butanol, ethylacetate, chloroform 등에는 녹지 않는 수용성 물질이었다. 물을 용매로 UV 흡광도를 측정한 결과 194nm에서 최대 흡광도를 나타내었다. 본 tyrosinase 저해제는 Iodine, Ninhydrin, Millon, Sakaguchi, Xanthoproteic, Emerson 시험에서는 음성이었고, Molish, Benedict, conc. $H_2SO_4$, $KMnO_4$ 시험에서는 양성이었다. 저해제의 열 안정성은 $100^{\circ}C$ 50분까지 안정하였고, pH $4{\sim}9$에서 안정하였다. Tyrosinase 저해제의 mushroom tyrosinase에 대한 $IC_{50}$ 값은 $19.2{\mu}g/ml$이었고, Streptomyces bikiniensis NRRL B-1049에 대한 저해활성은 $1,000{\mu}g/ml$ 일 때 27mm이었다. 그리고 본 저해제의 저해 양상은 경쟁적 저해로 확인되었다.

• 대한환경공학회지
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• 제30권6호
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• pp.637-641
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• 2008

이 연구는 과염소산염 제거를 위하여 정수처리장에서 적용 가능한 맞춤분말활성탄 제조와 활성탄 종류에 따른 제거효율 은 비교하기 위하여 수행하였다. Cetyltrimethylammoniumchloride(CTAC)를 이용하여 활성탄에 흡착 전처리하면 과염소산염을 효과적으로 제거 할 수 있었다. 10,000 mg/L 맞춤분활성탄은 농도 5,000 mg/L CTAC 용액 500 mL에 5 g의 분말활성탄을 혼합하여 제조하였다. 맞춤분말활성탄을 이용하면 일반 분말활성탄에 비해 10 이상 높은 과염소산염 제거가 가능하였다. 맞춤 분말활성탄을 이용하여 과염소산염 제거 시 초기 접촉시간 15분은 접촉시간에 따라 잔류 과염소산염의 농도가 줄어들었으나 15분 이후에는 잔류농도의 변화가 거의 없었다. 맞춤분말활성탄 조제 시 활성탄의 요오드가에 따라서 과염소산염 제거능이 달랐는데 요오드가 1,083 mg/g 활성탄은 요오드가 944 mg/g 활성탄에 비해 4배 이상 높은 과염소산염 제거능을 보였다. 일반적으로 정수장에서 주입 가능한 분말활성탄 농도인 5 mg/L 범위의 맞춤분말활성탄 주입농도에서 50 $\mu$g/L의 과염소산염 농도를 15 $\mu$g/L까지 저감 가능하였다.

• Journal of Radiation Protection and Research
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• 제45권3호
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• pp.101-107
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• 2020

Background: An important lesson learned from the Fukushima accident is that the transition to the mid- and long-term phases from the emergency-response phase requires less than a year, which is not very long. It is necessary to know how much radioactive material has been deposited in an urban area to establish mid- and long-term countermeasures after a radioactive accident. Therefore, an urban deposition model that can indicate the site-specific characteristics must be developed. Materials and Methods: In this study, the generalized urban deposition velocity and the subsequent variation in radionuclide contamination were estimated based on the characteristics of the Korean urban environment. Furthermore, the application of the obtained generalized deposition velocity in a hypothetical scenario was investigated. Results and Discussion: The generalized deposition velocities of ¹³⁷Cs, ¹⁰⁶Ru, and ¹³¹I for each residence type were obtained using three-dimensional (3D) modeling. For all residence types, the deposition velocities of ¹³¹I are greater than those of ¹⁰⁶Ru and ¹³⁷Cs. In addition, we calculated the generalized deposition velocities for each residential types. Iodine was the most deposited nuclide during initial deposition. However, the concentration of iodine in urban environment drastically decreases owing to its relatively shorter half-life than ¹⁰⁶Ru and ¹³⁷Cs. Furthermore, the amount of radioactive material deposited in nonresidential areas, especially in parks and schools, is more than that deposited in residential areas. Conclusion: In this study, the generalized urban deposition velocities and the subsequent deposition changes were estimated for the Korean urban environment. The 3D modeling was performed for each type of urban residential area, and the average deposition velocity was obtained and applied to a hypothetical accident. Based on the estimated deposition velocities, the decision-making systems can be improved for responding to radioactive contamination in urban areas. Furthermore, this study can be useful to predict the radiological dose in case of large-scale urban contamination and can support decision-making for long-term measurement after nuclear accident.

• 한국식품영양과학회지
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• 제21권2호
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• pp.195-200
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• 1992

Rhizopus oryzae CJ-2114가 생성하는 polygalactur-onase의 최대활성을 위한 pH는 4.0, 최적온도는 4$0^{\circ}C$ 였으며, 효소활성화 에너지는 2.049㎉/㏖이었다. 정제효소의 Km값과 $V_{max}$ 값은 54.05mM, 13.9m mole/min이었고, pectin보다 polygalacturonic acid를 특이적으로 분해하였다. 이 효소는 약산성의 pH에서 안정성을 보였으며, 온도에 의한 안정성은 4$0^{\circ}C$였으며, 5$0^{\circ}C$이상에서는 급격한 효소단백질의 불활성화가 진행되었다. 금속이온중 $Na^{+}$ 이온에 의해 활성이 유지되며 C $u^{2+}$, P $b^{2+}$, $Mn^{2+}$, $Zn^{2+}$이온 등은 효소활성을 저해하였다. 효소저해제 중 maleic anhydride와 iodine등에 의해 효소활성이 저해되어 효소분자중의 histidine의 imidazole기 와 cystein의 SH기가 효소활성에 관여함이 입증되었다. 이 효소의 기질분해양상을 여지 크로마토그라피로 확인한 결과 반응초기에는 monomer, dimer, oligomer 등이 생성되었고, 시간이 경과할수록 oligomer는 사라지고 monomer, dimer만이 생성되는 것으로 보아 endo 형인 것으로 판단되었으며, 효소의 과즙청징도 측정에서는 약 18.2$\times$$10^3$unit에서 거의 청징화 되었다.