The physicochemical properties of the emulsions prepared with four different proteins (pea protein isolate, whey protein isolate, soy protein concentrate, and soy protein isolate) were characterized in terms of particle size, rheological property, and freeze-thaw stability, while the feasibility of the protein-stabilized emulsions as a fat replacer was evaluated. Confocal laser scanning microscopic analysis showed that O/W emulsions were successfully prepared with all the proteins; however, the smallest particle size and excellent syneresis were observed in the WPI-stabilized emulsions. The use of WPI-stabilized emulsions as an alternative for shortening up to 50% level did not lead to differences in the muffin batters’ specific gravity and viscoelastic properties. After baking, the substitution of shortening with the WPI emulsions at up to 50% by weight did not significantly affect the muffins’ specific volume and texture characteristics.

This laboratory study was conducted to evaluate the effects of oyster shell by-product (OSB) on the characteristics of Hanwoo cow manure and emitted gases. For the treated groups, 0.5% and 1% OSB were applied to 200 g of Hanwoo cow manure in a container box with three replications each per group with a group without OSB (0%) as a control group. All samples were stored at room temperature to analyze pH, volatile basic nitrogen (VBN), volatile fatty acid (VFA), and gas emissions (NH3 and H2S) from Hanwoo manure on 0, 2, 4, and 8 days. No group exhibited a significant (p>0.05) effect on VBN, acetate, and propionate values during the 8 days. On day 0, pH increased by 1% OSB application, but no effects on the other days. Iso-butyrate concentration increased (p<0.05) on day 0 by OSB application, but deceased (p<0.05) on day 8. The NH3 gas emission on day 2 decreased (p<0.05) in all treatments applied OSB. However, either NH3 or H2S gases in all treatments were below 0.25 ppm on days 4 and 8, which were no differences (p>0.05) among treatments. Thus, this lab study indicated that the inclusion of OSB application in Hanwoo cow manure had a beneficial effect on NH3 gas emission, but no longer than for 2 days.

The purpose of this study was to investigate the Maillard reaction–related physicochemical properties of three maize varieties (Kwangpyeongok, Sinhwangok2ho and Gangdaok) after roasting them for different times (0, 15, 25, 40, and 55 minutes). The Maillard reaction is a non-enzymatic browning reaction involving reducing sugars and amino compounds. The content of reducing sugar, the causative agent of the Maillard reaction, decreased as roasting time increased. Gangdaok showed the lowest reducing sugar content of 1.04 mg/g after 55 minutes of roasting. In the elapsed roasting time, chromaticity ‘L’ and ‘b’ values decreased. At 55 minutes of roasting, wherein the Maillard reaction occurred most actively, Gangdaok showed the lowest ‘L’ value of 56.37 and the highest ‘a’ value of 7.60. Gangdaok had superior conditions for inducing the Maillard reaction compared to other varieties, and it is consider that 'flint–type', an endosperm characteristic, may have been the influencing agent. This study detected a total of 52 types of volatile aroma compounds (VACs), of which 28 were produced after roasting. Of the total VACs detected, 2-Formyl-5-methylfuran and 2-Furancarboxaldehyde accounted for 43.8~45.5% and have been confirmed to be the major VACs present in roasted maize. Most of the correlations between the Maillard reaction–related characteristics showed high correlation coefficients.

The purpose of this study was to develop a functional beverage by using Caragana sinica extract and Tremella fuciformis Berk, which have high physiological effects such as anti-diabetic, antioxidant, anticancer, anti-lipidemic and anti-inflammatory. To this end, we used various mixing ratios of Caragana sinica extract, Tremella fuciformis Berk, and isomalto oligosaccharide, and measured the physicochemical properties of those beverages. The analyses showed the following: moisture content of those beverages using Caragana sinica extract and Tremella fuciformis Berk was 50.51~67.64%, pH was 5.19~5.38, and crude fat content was 0.28~0.52%, crude protein content was 1.26~1.80%, ash content was 0.47~0.80 and sugar content was 8.55~26.98°Brix. The lightness (L) of the beverages was 37.70~58.11, the redness (a) was 6.88~16.94, the yellowness (b) was 13.72~23.68, the total polyphenol content was 2.07~3.46 mg/g, and the total flavonoid content was 0.37~0.42 mg/g. Based on the results, it was confirmed that the nutritional components and total polyphenols of functional beverage using Caragana Sinica Extract, Tremella Fuciformis Berk and isomalto oligosaccharide were high at a mixing ratio of 1:1.3:25%. These results will increase the use of Caragana Sinica Extract and Tremella Fuciformis Berk, as functional materials in the future, and provide a framework for the manufacturing of diluted beverages comprising mineral water and carbonated water.

Deep geological disposal is generally accepted to be the most practical approach to handling radioactive wastes. Bentonite has been considered as a buffer material in deep geological disposal repositories (DGR) for high-level radioactive wastes. Evaluating the effect of short-term bentonite alteration on EBS performance has limitations in safety assessment over thousands of years. Information on bentonite characteristics under various conditions obtained from natural systems can be used to evaluate long-term safety of bentonite buffer. The purpose of this study was to investigate mineralogical and physicochemical characteristics of bentonite in the Naah mine located in Yangnam-myeon, Gyeongju-si for a natural analogue of the bentonite barrier in DGR. A total of 15 samples were collected at regular intervals from the bentonite layer and andesitic lapilli tuff (i.e., parent rock) at the boundary with the bentonite layer. The bentonite layer is located at a depth of about 1 m below the ground surface. Each sample was separated into particles < < 75 μm and particles < 2 μm through grinding and sedimentation processes. The separated subsamples were characterized mineralogically and physiochemically using various analytic techniques. Bentonite samples have a similar SiO2/Al2O3 ratio to the parent rock and a lower (Na+K)/Si ratio than the parent rock, indicating depletion of alkali components during bentonitization. The parent rock and bentonite samples have similar mineral composition (i.e., quartz, feldspars, opal-cristobalite-tridymite and montmorillonite). Results of XRD analysis on the randomly distributed particles < 2 μm indicate that bentonite is mostly composed of Ca-montmorillonite, which is a typical dioctahedral smectite. Results of FTIR and VNIR analysis indicate that montmorillonite contained in bentonite is Al-dioctahedral montmorillonite, and Al is substituted with Mg in some octahedron units. The mineralogical and physicochemical characteristics are similar regardless of sampling location. These results suggest that bentonite potentially exposed to weathering, located near the ground surface, has hardly altered.

To minimize the short-term thermal load on the repository facility, heat generating nuclides such as Cs-137 and Sr-90 should be separated from the spent nuclear fuel for efficiency of repository facility. In particular, Sr-90 must be separated because it generates high heat during the decay process. Recently, Korea Atomic Energy Research Institute (KEARI) is developing a waste burden minimization technology to reduce the environmental burden caused by the disposal of spent nuclear fuel and maximize the utilization of the disposal facility. The technology includes a nuclide management process that can maximize disposal efficiency by selectively separating and collecting major nuclides such as Cs, Sr, I, TRU/RE, and Tc/Se from spent nuclear fuel. Among the major nuclides, Sr nuclides dissolve in chloride phase during the chlorination process of spent nuclear fuel and recovered in the form of carbonate or oxide via reactive distillation. In this process, Ba nuclides are also recovered along with Sr nuclides due to their chemical similarity. In this study, we prepared group II nuclide ceramic waste form, Ba(x)Sr(1-x)TiO3 (x=0, 0.25, 0.5, 0.75, 1), using the solid-state reaction method by considering the various ratio of Sr/Ba nuclides generated from nuclide management process. The established waste form fabrication process was able to produce a stable waste form regardless of the ratio of Sr/Ba nuclides. To evaluate the stability of group II waste form, physicochemical properties such as leaching and thermal properties were evaluated. Also, the radiological properties of the Ba(x)Sr(1-x)TiO3 waste forms with various Sr/Ba ratios were evaluated, and the estimation of centerline temperature was carried out using the experimental thermal property data. These results provided fundamental data for long-term storage and management of group II nuclides waste form.

본 연구는 한우 암송아지 비육프로그램 개발을 위하여 약 8개월령 30두(평균 체중 233kg)에게 전 시험기간동안 한우 거세우 육성용 사료(CP 13.65%, TDN 72.7% 건물기 준)를 자유채식 또는, 제한급여(체중의 1.5%, 1.6%/일)를 시킨 후, 24개월령부터 출하 시(32개월령)까지는 자유 채 식시켰다. 본 시험에서 출하 시 체중은 685-702kg 이었으 며, 전 기간 평균 사료 섭취량(7.78–9.05kg/일)과 증체량 (0.58–0.64kg/일)은 자유채식구가 제한급여구보다 많았다 (p<0.05). 한우 미경산 암소의 배최장근 단면적은 평균 99.9cm2였으며, 도체중은 평균 407kg이었다. 조리 감량은 수분함량이 높고 보수력이 낮을수록 많았다(p<0.05). 등심 중 아미노산 함량은 glutamic acid, aspartic acid, lysine, leucine 순으로 높았으며, 지방산 중에는 oleic acid가 55.9 –58.7% 수준으로 자유채식구가 제한급여구보다 높았다 (p<0.05). 따라서 한우암소 비육 프로그램으로서, 한우 거세우 육 성용 TMR을 전 기간(6-32개월령) 동안 자유 채식시키면, 사료효율, 도체 성적 및 등심의 물리·화학적 특성에 있어 서도 우수한 결과를 나타낼 수 있을 것으로 판단된다.

This study compared the physicochemical and gelatinization properties of naked barley, tetrastichum barley, and waxy barley. Compared to tetrastichum barley and waxy barley, naked barley had shorter and rounder grains with a 1.43 length/ width ratio. Tetrastichum barley had lower crude protein, crude lipid, and crude ash content and higher amylose content compared to naked barley and waxy barley. The L, a, b color values of waxy barley were significantly higher than those of naked barley and tetrastichum barley. The water absorption index (WAI) and the water soluble index (WSI) were highest in waxy barley. The X-ray diffraction pattern was type A in all samples, and the peak intensity was highest in waxy barley. The maximum viscosity, cooling viscosity, breakdown, and setback of amylogram properties were the highest in tetrastichum barley. The thermal properties through the differential scanning calorimeter showed that the waxy barley had higher values of the onset, peak, conclusion temperature and enthalpy (?H). In conclusion, the variety of barley influenced the physicochemical and gelatinization properties, which could be important factors in the manufacture of processed foods. These results would thus useful inputs for the manufacturing of these foods using barley.

Sulfate-rich waste powder containing a radioactive nuclide is generated from chemical decontamination process and radioactive liquid waste treatment using ion exchange resin. The radioactive sulfate-rich waste powder should be stabilized for final disposal. The techniques for immobilization of the radioactive sulfate-rich waste powder such as hydraulic cement, geopolymer, and iron phosphate glass have been applied, however, there are limitation in these techniques. Firstly, the hydraulic cement cannot applied to the wastes containing high concentration of sulfate because the expansion, cracks, and disintegration can be happened in the waste form. Geopolymer has a low density although they can be used as a good binder. The iron phosphate glass can be utilized, however, a considerable amount of SO2 gas is emitted due to the high sintering temperature. In this study, immobilization of radioactive sulfate-rich waste powder was carried out to resolve above problems by applying low temperature sintering method using a low-melting glass. As a result, it was confirmed that the waste form has a high bulk density. The compressive strength of the waste form was over 40 MPa, which is higher than the acceptance criteria (≥ 3.44 MPa). From ANS 16.1 test, it was verified that the waste form met the acceptance criteria of the leachability index (≥ 6). It was also confirmed that the waste form was chemically durable through product consistency test (PCT). In addition, the chemical stabilities of waste forms were compared following the sintering condition and the composition of the waste forms. The difference of the chemical stability was explained by difference in the abundance of chemical form obtained from the sequential extraction test.

To reduce the environmental burden caused by the disposal of spent nuclear fuel and maximize the utilization of the repository facility, waste burden minimization technology is currently being developed at the Korea Atomic Energy Research Institute (KEARI). The technology includes a nuclide management process that can maximize disposal efficiency by selectively separating and collecting major nuclides in spent nuclear fuel. In addition, for efficient storage facility utilization, the short-term decay heat generated by spent nuclear fuel must be removed from the waste stream. To minimize the short-term thermal load on the repository facility, it is necessary to separate heat generating nuclides such as Cs-137 and Sr-90 from the spent fuel. In particular, Sr-90 must be separated because it generates high heat during the decay process. KAERI has developed a technology for separating Sr nuclides from Group II nuclides separated through the nuclide management process. In this study, we prepared Sr ceramic waste form, SrTiO3, by using the solid-state reaction method for long-term storage for the decay of separated Sr nuclides and evaluated the physicochemical properties of the waste form. Also, the radiological and thermal characteristics of the Sr waste form were evaluated by predicting the composition of Sr nuclides separated through the nuclide management process, and the estimation of centerline temperature was carried out using the experimental thermal data and steady state conduction equation in a long and solid cylinder type waste form. These results provided fundamental data for long-term storage and management of Sr waste.

Comparing the quality characteristics of kimchi were measured and anticancer effects using AGS human gastric cancer cells were observed. Five kinds of kimchi samples were made of Kanghwa Baek kimchi (KB), Kangwha Turnip kimchi (KT), Turnip: Chinese cabbage = 1:1 Baek kimchi (T1B1), Turnip:Chinese cabbage = 4:1 Baek kimchi (T4B1), Turnip mul kimchi (T). As a result T kimchi showed the best fermentation characteristics among the five samples. T kimchi had a lower percentage of the total number of aerobic bacteria, while the number of lactobacillus was higher than that of other samples. The mRNA and protein expression levels of apoptosis-related factors found that T kimchi significantly increases the mRNA expression levels of caspases-3 and caspases-9 in AGS human gastric cancer cells as compared to the other kimchi samples. It showed high anticancer effects in the order of T, T1B1, and KB kimchi. As the anticancer effect of Turnip mul kimchi made only of turnip was higher, the higher the turnip content, the higher the anticancer effect. These results show that there were changes in fermentation characteristics such as pH, acidity, number of lactic acid bacteria, and anticancer effects according to the ratio of turnip and cabbage.