In KAERI, the nuclide management technology is currently being developed for the reduction of disposal area required for spent fuel management. Among the all fission products of interest, Cs, I, Kr, Tc are considered to be significantly removed by following mid-temperature and hightemperature treatment, however, a difficulty of real spent-fuel thermal treatment experiment limits the development of such thermal treatment. The test employing SimFuel (Simulated Spent Fuel) can be an alternative for such condition, however, the fabrication of SimFuel containing semivolatile species such as Cs, I and Re (substitute for Tc) was not achieved for conventional sintering method since such species are easily removed during hot temperature treatment. In this study, for the prevention of volatilization of such species and the inclusion of semi-volatile species in fabrication of SimFuel, argon-based high pressurizing up to Max 100 bar was considered to be applied in high temperature treatment. For this, lab-scale hot-isostatic press applicable up to 1,500°C was fabricated and is being waiting for the approval for high-pressure test. After approval of license, UO2 baesd SimFuel containing CsI will be fabricated and its micro-structure and composition will be evaluated through SEM-EDX and XRD

The stabilization techniques are highly required for damaged nuclear fuel to strengthen safety in terms of transportation, storage, and disposal. This technique includes recovering fuel materials from spent fuel, fabrication of stabilized pellets, and fabrication of fuel rods. Thus, it is important to identify the leaching behavior of the stabilized pellets to verify their stability in humid environments which are similar to storage conditions. In this study, we introduce various leaching experiment methods to evaluate the leaching behavior of the stabilized pellets, and determine the most suitable leaching test methods for the pellets. Also, we establish the leaching test conditions with various factors that can affect the dissolution and leaching behavior of the stabilized pellets. Accordingly, we prepare the simulated high- (55 GWd/tU) and low- (35 GWd/tU) burnup nuclear fuel (SIMFUEL) and pure UO2 pellets sintered at 1,550°C and 1,700°C, respectively. Each pellet is placed in a vessel and filled with DI water and perform the leaching test at three different temperature to verify the leaching mechanism at different temperature range. Based on the standard leaching test method (ASTM C1308-21), the test solution is removed from the pellet after specific time intervals and replaced in the fresh water, and the vessel is placed back into the controlled-temperature ovens. The test solutions are analyzed by using ICP-MS.

The Ag0-containing sorbents synthesized by Na, Al, and Si alkoxides have higher maximum iodine capture capacity and textural properties than zeolite-based Ag0-containing sorbents. However, these sorbents were prepared in the form of granules via a step for cutting cylindrical alcogels. Since asmade sorbents decreased packing density, they must be additionally crushed and then classified into an appropriate size for increasing packing density. The bead formation in the step of sol-gelation could bring about the simplification of sorbent preparation process and an improvement of packing density. In the Na, Al, and Si alkoxides as starting materials, sol solution was hydrophilic and lower density than vegetable oil, which transformed sol droplets to sol-gel beads. Thus, in these precursors, sol droplets, which must be sprayed by single nozzle placed at bottom side of oil column, can rise up through oil column. Acetic acid (HOAc) was used as the catalyst for the hydrolysis of Na alkoxide (TEOS) and gelation of the Na+AlSi-OH alcosol. For obtaining sol-gel beads, experiments were performed by the flowrate change of sol solution and HOAc at different nozzle sizes using soybean oil column of 1 m in length. At a sol/HOAc flowrate ratio of 3.85, some Na+AlSi-OH alcogel beads were obtained. After the Ag/Na ion-exchange, Ag content in Ag+AlSi-OH hydrogel was low due to reaction between Na+ and HOAc during sol-gelation and aging step. The Ag+AlSi-OH hydrogel with high Ag content could be prepared by Na addition. After the solvent exchange and drying at ambient pressure, the bead sorbents had higher Ag0 content and larger pore size than granular sorbents. However, further experiments are needed to increase yield rate in bead sorbent.

When damaged nuclear fuel is stripped and re-fabricated into stabilized pellets, it is necessary to analyze the characteristics of the stabilized pellets, such as density, leaching behavior, and compressive strength, for final disposal. In this study, simulated nuclear fuel with UO2 and burn-up of 35 GWd/tU and 55 GWd/tU was used to measure the compressive strength of the stabilization pellet. In order to change the density of the sintered pellet, a sintered pellet was prepared by heat treatment at 1,550°C and 1,700°C for 6 hours in a reducing atmosphere of 4% H2/Ar. In the case of UO2, the density was 10.4 g/cm3 (94.5% of T.D.) and 10.6 g/cm3 (96.6% of T.D.) depending on the sintering temperature (1,550°C, 1,700°C). In the case of simulated fuel with a burn-up of 35 GWd/tU, the density was 8.8 g/cm3 (80.9% of T.D.) and 10.2 g/cm3 (93.6% of T.D.) depending on the sintering temperature (1,550°C, 1,700°C). In the case of simulated fuel with a burn-up of 55 GWd/tU, the density was 8.3 g/cm3 (77.0% of T.D.) and 10.0 g/cm3 (92.3% of T.D.) depending on the sintering temperature (1,550°C, 1,700°C). It was found that the compressive strength of simulated nuclear fuel decreased with increasing burn-up and increased with increasing density. In the case of UO2, the compressive strengths were 717.8 MPa and 897.4 MPa when the densities were 10.4 g/cm3 and 10.6 g.cm3, respectively. In the case of simulated nuclear fuel with a burn-up of 35 GWd/tU, the compressive strengths were 472.1 MPa and 732.3 MPa when the densities were 8.8 g/cm3 and 10.2 g/cm3. In the case of simulated nuclear fuel with a burn-up of 55 GWd/tU, the compressive strengths were 301.4 MPa and 515.5 MPa when the densities were 8.3 g/cm3 and 10.0 g/cm3, respectively.

Irradiated uranium dioxide in damaged used fuel could oxidize during transportation, interim storage or disposal, resulting that the fuel pellet fragments are reduced to a grain-sized powder that can easily escaped from the damaged rod. It has been reported that oxidized spent fuel (i.e. U4O9+x) that was in contact with water could increase the dissolution rate by making the grain boundaries more accessible to the water. Therefore, the damaged used fuel requires stabilization technology including nuclear material recovery, pellet manufacturing process, and stabilization fuel rod manufacturing that can secure safety in terms of permanent disposal. In this study, we prepared pure UO2 and SIMFUEL pellets that are a mixture of UO2 and surrogated metallic oxides for fission products equivalent to a burn-up of 35 GWd/tU and 55 GWd/tU as the stabilized spent fuel. The UO2 and fission products powders were milled and pressed into pellets at 250 MPa and sintered at 1,550°C and 1,700°C for 6 hours in an atmosphere of 4%H2-Ar. The prepared UO2 and SIMFUEL pellets were placed in PTFE Teflon vessels and filled with deionized water to identify the leaching behavior by a long-term leaching experiment under the similar condition to a repository for the safe disposal.

The Na, Al, and Si akoxides-based sorbents for iodine capture have higher maximum iodine capture capacity and pore properties than zeolite-based sorbents. However, these sorbents were prepared in the form of granules via a step for cutting cylindrical alcogels. Since as-made sorbents decreased packing density, they must be additionally crushed and then classified into an appropriate size for increasing packing density. The bead formation in the step of sol-gelation could bring about the simplification of sorbent fabrication process and an improvement of packing density. For the formation of gel bead, characteristics such as hydrophilic or hydrophobic property and density of sol solution were investigated to design sol-gelation equipment. The sol-gel bead preparation equipment in the reflection of sol solution characteristics was fabricated through selection of oil for formation of sol bead, solvent for collection of gel bead, and nozzle for spray of sol droplet formation. The continuous or discontinuous formation of sol beads from NaAlSi-OH sol solution were observed according to flow rates of 6 to 8 mL·min−1 and nozzle diameters of 0.4 to 0.8 mm. In the sphericity of sol bead, the best sol beads were obtained from 0.5 mm nozzle without clogging by sol solution in the flow rate range of 6–8·min−1.

1913년부터 2013년까지 국내에서 육성된 172품종에 대한 종실의 단백질, 지방 함량과 지방산 조성의 변이는 다음과 같다. 총 단백질 함량의 평균은 38.6%(31.6~45.3%), 지방함량의 평균은 18.4%(15.3~21.5%), 포화지방산 중 Palmitic acid의 함량은 평균11.11%(8.1~13.5%), Stearic acid의 함량은 평균 3.7%(1.9~5.4%), 불포화지방산인 Oleic acid의 함량은 평균 26.4%(13.1~41.8%), Linoleic acid의 함량은 평균 50.9% (37.2~63.0%), Linolenic acid의 함량은 평균 7.6%(5.7~9.8%), Linoleic(ω-6)/Linolenic(ω-3)acid의 비율은 평균 6.8(5.3~8.9)이여서, 포화지방산이 평균 14.8%(10.8~17.6%), 그리고 불포화 지방산 함량은 평균 84.9%(79.9~88.7%)이었다. 단백질 함량이 가장 높은 품종은 45.3%로 새단백콩이었으며, 지방함량이 가장 높은 품종은 21.5%를 함유한 늘찬콩이었다. 고 Oleic acid 함량인 동시에 저 Linoleic acid 함량인 검정콩1호는 양질의 지방산을 함유한 매우 유용한 품종이었다. 용도에 따른 단백질, 지방 지방산의 평균함량 중 단백질의 함량은 풋콩 및 올콩용 품종이 가장 높았고, 지방 함량은 장류용 품종이 가장 높았으며, 포화지방산은 장류용품종이 가장 낮았고, 불포화지방산의 함량은 풋콩 및 올콩용 품종이 가장 낮았다. ω-6/ω-3의 비율은 밥밑용 품종이 가장 낮았다. 종피색에 따라서는 단백질 함량은 녹색콩이 가장 높았으며 지방함량은 황색콩이 가장 높았다. 포화지방산은 황색콩과 검정콩이 가장 낮았으며, 불포화 지방산은 갈색콩이 ω-6/ω-3의 비율 또한 갈색콩이 가장 낮게 나타났다.

The high theoretical energy density (2600 Wh kg−1) of Lithium-sulfur batteries and the high theoretical capacity of elemental sulfur (1672 mAh g−1) attract significant research attention. However, the poor electrical conductivity of sulfur and the polysulfide shuttle effect are chronic problems resulting in low sulfur utilization and poor cycling stability. In this study, we address these problems by coating a polyethylene separator with a layer of activated carbon powder. A lithium-sulfur cell containing the activated carbon powder-coated separator exhibits an initial specific discharge capacity of 1400 mAh g−1 at 0.1 C, and retains 63% of the initial capacity after 100 cycles at 0.2 C, whereas the equivalent cell with a bare separator exhibits a 1200 mAh g−1 initial specific discharge capacity, and 50% capacity retention under the same conditions. The activated carbon powder-coated separator also enhances the rate capability. These results indicate that the microstructure of the activated carbon powder layer provides space for the sulfur redox reaction and facilitates fast electron transport. Concurrently, the activated carbon powder layer traps and reutilizes any polysulfides dissolved in the electrolyte. The approach presented here provides insights for overcoming the problems associated with lithium-sulfur batteries and promoting their practical use.

Unlike common nouns, proper nouns do not depend on the situation. So a proper noun is defined as either pointing to a particular object or pointing to a single object. In philosophy, these proper nouns have been known to play an important role in linking objects only to language and language extrinsic targets. For these reasons, however, proper nouns were not considered as important in foreign language education. However, after ‘the pragmatic turn of linguistics’ in the early 1960s, communication-oriented foreign language education became important. Because communication is closely related to the concept of culture, and culture and proper nouns are closely related. The purpose of this paper is to examine the status of proper nouns in the basic vocabulary of the second foreign language curriculum and how these proper nouns are presented in the College Entrance Trial Test/College Scholastic Ability Test. This paper seeks to analyze how often the same proper nouns are repeated in the test, how the proper nouns are translated, and whether such translations are consistent. Im Gegensatz zu gewöhnlichen Substantiven sind Eigennamen nicht von der Situation abhängig. Ein Eigenname ist also definiert als entweder auf ein bestimmtes Objekt zeigend oder auf ein einzelnes Objekt zeigend. In der Philosophie ist bekannt, dass diese Eigennamen eine wichtige Rolle bei der Verknüpfung von Objekten nur mit extrinsischen Zielsetzungen von Sprache und Sprache spielen. Aus diesen Gründen wurden Eigennamen im Fremdsprachenunterricht jedoch nicht als wichtig erachtet. Nach der “pragmatischen Wende der Linguistik” in den frühen 1960er Jahren wurde jedoch der kommunikationsorientierte Fremdsprachenunterricht wichtig. Es ist wichtig zu beachten, dass es eine enge Beziehung zwischen Kommunikation und Kultur gibt. Kultur und Eigennamen haben miteinander zu tun. Der Zweck dieses Artikels ist es, den Status von Eigennamen im Vokabular des zweiten Fremdsprachenlehrplans zu untersuchen und wie diese Eigennamen im College Entrance Trial Test / College Scholastic Ability Test dargestellt werden. Diese Arbeit versucht zu analysieren, wie oft dieselben Eigennamen im Test wiederholt werden, wie die Eigennamen übersetzt werden und ob solche Übersetzungen konsistent sind.

KAERI의 PRIDE 시설에서 공학규모의 전해환원용 원료물질인 UO2 다공성펠렛 제조를 위해 공정과 장치를 최적화시킨 내 용을 다루었다. UO2 분말과 별도로 attrition 밀링된 대용산화물 분말을 출발분말로, 정밀 칭량을 통해 사용후핵연료 조성을 모사하였다(Simfuel). Simfuel 분말은 각각 tumbling mixer로 혼합하여 균질화 하고, rotary press로 성형하여 furnace를 이 용해 소결하였다. 4% H2-Ar 분위기에서 1450℃ 24시간 고온 열처리하여 제조된 소결펠렛은 6.89 g·cm-3의 벌크밀도를 가 지며 이는 후속 전해환원 공정의 요구에 부합한다. 소결된 다공성펠렛의 미세구조 관찰을 통해 다공성 기지상과 함께 산화/ 금속 석출물이 관찰되어 사용후핵연료의 상이 모사됨을 확인하였다. 본 결과는 향후 공학규모 이상의 파이로 연구를 위한 UO2 다공성펠렛 제조에 중요한 기초자료로 활용 될 것이다.

The objective of this study was to investigate ELF-MF exposure levels of the elderly groups in their living environments using 24-hour personal measurement. In addition, EMF risk perception was investigated. Through evaluations of ELF-MF exposure levels in the proximity of the participants of 58 elderly groups, it was found that TWAam was 1.31 mG (TWAgm: 0.84). ELF-MF exposure levels of the elderly group that live in the proximity of a non-visible power line was high, but there were no statistically significant differences between the non-visible power line elderly group and visible power line elderly group. Moreover, there were no statistically significant differences in ELF-MF exposure according to gender, age, city classification, incomes, residence type, and size. The results showed that the perception of the ELF-MF was very low, as indicated by more than roughly 58.6% of the elderly surveyed saying that they did not know what ELF-MF was. In addition, there was no awareness among the group of how to avoid behavior of EMF from some electric equipment and facilities. Thus, these results will provide useful data for the determination of ELF-MF management and risk communication methods in the living environment for elderly people.