Paecilomyces tenuipes (P. tenuipes) is a fungus cultivated artificially by South Korean researchers, utilizing rice bran as its substrate. The increased demand for this fungus has not been met with successful cultivation methods for fruiting body production in natural environments. Therefore, we tested the effect on the growth of P. tenuipes using a Solid media based on pests. In this results, the Solid media based on M.alternatus was effective in increasing the growth of P. tenuipes and the content of cordycepin. Moreover, we confirmed the conditions for manufacturing a Solid media based on M.alternatus for P. tenuipes growth. We suggested that the growth-promoting compounds offers valuable insights for optimizing fungal cultivation conditions, thereby enhancing productivity and contributing to a broader understanding of fungal physiology in varying nutritional environments.

Background: The biological information of fish, which include reproduction, is the prerequisite and the basis for the assessment of fisheries. Methods: The aim of this work was to know the reproductive biology with the first sexual maturity (TL50) and the spawning period for 58 mainly fish species in the waters around La Réunion Island (Western Indian Ocean). Twenty families belonging to the Actinopterygii were represented (acanthuridae, berycidae, bramidae, carangidae, cirrhitidae, gempylidae, holocentridae, kyphosidae, labridae, lethrinidae, lutjanidae, malacanthidae, monacanthidae, mullidae, polymixiidae, pomacentridae, scaridae, scorpaenidae, serranidae, sparidae; 56 species; n = 9,751) and two families belonging to the Elasmobranchii (squalidae, centrophoridae; 2 species; n = 781) were sampled. Between 2014 and 2022, 10,532 individuals were sampled covering the maximum months number to follow the reproduction periods of these species. Results: TL50 for the males and the females, respectively, ranged from 103.9 cm (Acanthurus triostegus ) to 1,119.3 cm (Thyrsitoides marleyi ) and from 111.7 cm (A. triostegus ) to 613.1 cm (Centrophorus moluccensis ). The reproduction period could be very different between the species from the very tight peak to a large peak covered all months. Conclusions: Most species breed between October and March but it was not the trend for all species around La Réunion Island.

Exploring cheap and efficient oxygen evolution reaction (OER) catalysts is extremely vital for the commercial application of advanced energy storage and conversion systems. Herein, a self-supporting Co3S4/ S-doped reduced graphene oxide ( Co3S4/S-rGO) film catalyst is successfully prepared by a blade coating coupled with high-temperature annealing strategy, and its morphology, structure and composition are measured and analyzed. It is substantiated that the as-synthesized Co3S4/ S-rGO film possesses unique self-supporting structure, and is composed of uniformly dispersed Co3S4 nanoparticles and highly conductive S-rGO, which benefit the exposure of catalytic sites and electron transfer. By reason of the synergistic effect of the two individual components, the self-supporting Co3S4/ S-rGO film catalyst displays outstanding catalytic performance towards OER. As a consequence, the Co3S4/ S-rGO film catalyst delivers an overpotential of 341 mV at 10 mA cm-2, and the current attenuation rate is only 2.6% after continuous operation for 4 h, verifying excellent catalytic activity and durability. Clearly, our results offers a good example for the construction of high-performance self-supporting carbon-based composite film catalysts for critical electrocatalytic reactions.

소형 선박(<499 GT)이 전체 선박의 46%를 지배하고 있어 상대적으로 많은 CO2 배출가스를 가지고 있다고 결론지을 수 있다. 최 적의 Trim 조건에서 운전하면 선박의 저항을 감소시킬 수 있어 온실가스가 적게 발생할 수 있다. Trim을 최적화하는 가장 저렴한 방법 중 하 나는 최적의 Longitudal Center of Gravity(LCG)를 얻기 위해 무게 분포를 조정하는 것이다. 따라서 본 연구에서는 소형 선박의 저항에 대한 LCG 변화의 영향을 경험적 및 수치적 해석을 통해 연구하고자 한다. 선체를 설계하는 Savitsky 경험식은 Maxsurf Resistance의 방법으로 사용 된다. 수치해석에는 STAR-CCM+ 상용 CFD(Computational Fluid Dynamics) 소프트웨어가 사용되지만 최종적으로 선박 설계 과정 이후 최적의 LCG를 얻기 위해 전체 저항을 비교한다. 결론적으로 Froude Number 0.56에서는 수치해석에 의해 전체 길이(LoA) 46.2%에서 최적의 LCG를 달성하고 Froude Number 0.63에서는 43.4% LoA를 달성하여 29.2% LoA에서 기준점에 비해 최대 41.12% - 45.16%의 상당한 저항 감소를 얻을 수 있다.

프리지아 ‘Ruby Star’는 농촌진흥청 국립원예특작과학원 에서 보라색 홑꽃 ‘Avilla’와 흰색 반겹꽃 ‘Medeo’를 2012년 교배하여 얻은 종자로부터 2006년 향이 좋고 개화기가 빠른 적색 홑꽃 계통을 선발하여 품종으로 개발되었다. 2014년부 터 2017년까지 생육·개화 특성검정 및 육성계통평가회의 기 호도 평가를 거쳐 선발되었으며 2018년 직무육성품종심의회 를 통해 ‘Ruby Star’로 명명되어 2021년 신품종으로 등록되 었다. ‘Ruby Star’는 빨간색(RHS, R45A) 홑꽃인 절화용 프리 지아 품종으로 개화소요일수가 118.0일이며 초장이 120.5cm 로 대조품종 ‘Rapid Red’보다 약 28.7cm 더 길다. 주당 분 지수는 5.8개로 대조품종에 비해 수확량이 많고 첫번째 분지 의 길이가 32.0cm, 두께가 3.02mm로 절화 특성이 우수하 다. ‘Ruby Star’의 소화수 및 소화폭은 각각 14.8개, 6.3cm 로 소화수가 많은 중대형화이다. 절화수명은 약 8.4일이며 주 당 자구수는 3.8개, 평균 자구중은 2.9g이다. 전자코를 이용 한 PCA 분석 결과 PC1과 PC2의 설명력은 각각 97.9%, 1.8%로 전체 변이의 99.7%를 반영했으며 ‘Ruby Star’와 대 조품종 ‘Rapid Red’는 서로 다른 향기 패턴을 보였다. Radar plot 결과 총 6개의 MOS 센서에서 ‘Ruby Star’의 센서 반응 이 ‘Rapid Red’보다 강하게 나타나 ‘Ruby Star’의 향기가 더 강한 것으로 나타났다.

백합 종간 교잡종은 다양한 교배 방법에 의해 생산되어지 고 있다. 그러나 이들 종간 교잡종은 대부분 불임이다. 2n gametes는 백합에서 종간 교잡종 F1의 불임을 극복할 수 있 을 뿐 아니라 우수한 유전형질을 지닌 2n과의 교배에 이용할 수 있고 후대 다양한 유전형질을 기대할 수 있다. 따라서 본 실험에서는 가장 효과적으로 2n gametes를 생산할 수 있는 방법을 구축하기 위하여 백합 Oriental hybrids ‘Medusa’와 ‘Marco Polo’에 N2O를 처리하였다. 같은 Oriental 그룹 내 에서도 ‘Medusa’와 ‘Marco Polo’는 화뢰 크기별 감수분열 시기가 달랐다. 감수분열 tetrad 시기에 염색체를 관찰한 결 과 sequential spindles, tripolar spindles에 의해 2가지 다른 형태가 관찰되었다. ‘Medusa’에서 2atm의 N2O를 처리 한 화뢰 길이 10~15mm와 20~25mm에서 monad, dyad, triad, tetrad가 관찰되었다. 그러나 4atm에서는 tetrad 이외에는 검경 되지 않았다. ‘Marco polo’의 경우 화뢰 길 이 10~15mm, 25~30mm 시기에 2, 4atm의 N2O를 12, 24 시간 동안 처리한 구에서 모두 dyad, triad가 관찰되었다. ‘Medusa’, ‘Marco Polo’ 모두 dyad, triad, tetrad가 관찰 된 시기는 대조구에서 interphase와 metaphase Ⅰ에 해당 하는 시기이다. 화분의 모양은 타원형으로 처리 전·후 변화가 없었으며 처리 후 화분의 크기는 n 보다 큰 화분뿐 아니라 작 은 화분도 관찰되어 전체적으로 다양했다. 화분의 임성과 발 아율은 처리구별로 차이가 없었으나 평균적으로 처리 후가 무처리구보다 임성은 약 10%, 발아는 약 20% 정도 떨어졌다. ‘Medusa’와 ‘Marco Polo’를 이용하여 N2O를 처리한 것과 처리하지 않은 것을 정역 교배하였을 때 자방이 비대 되는 형 태가 2가지이었으나 처리 별 차이는 아니었다. 획득된 식물체 를 Flow cytometry로 검정한 결과, 무처리 ‘Marco Polo’와 2atm 24시간 32mm에 처리한 ‘Medusa’의 교배를 통해 하 나의 식물체에서 2배체와 3배체가 모두 나오는 mixoploid를 확인할 수 있었다. 그 외 실험을 통해 얻은 식물체 중에서 이 수체가 4개 발견되었다. 확실한 3배체를 가진 식물체는 관찰 할 수 없었다.

수국은 수국과(Hydrangeaceae) 수국속(Hydrangea)의 낙엽관목 식물로 크고 화려한 화형을 가져 절화, 분화 및 조 경수로 전세계적 인기가 있는 식물이다. 나무수국은 수국 (H. macrophylla)과 비교하여 삽목율이 낮은 것으로 알려져 있지만 나무수국의 묘목생산을 위한 삽목 연구 및 두 종간 삽목율 차이 원인 규명에 관한 연구는 미미하다. 본 연구는 IBA(Indol-3-butyric acid) 500mg·L-1 처리시 삽수의 침지 시간에 따른 삽목율 조사를 통해 적정 호르몬 처리 시간을 제 시하고 나무수국과 수국의 해부학적 구조 관찰을 통한 삽목율 차이 발생의 원인을 규명하고자 실시하였다. 나무수국의 적정 호르몬 처리 시간을 규명하기 위해 IBA 500mg·L-1을 무처 리, 30분, 2시간, 4시간 침지처리를 하였다. 종간 삽목율 차이 발생의 원인 규명을 위해 나무수국과 수국의 줄기 단면과 삽 목 후 시간 경과에 따른 발근을 해부학적으로 관찰하였다. 연 구의 결과 나무수국의 삽목시 IBA 500mg·L-1에 2시간 이상 침지처리가 다른 처리구와 비교하여 발근율이 높고 발생 뿌리 수가 가장 많았다. 또, 나무수국의 삽목율이 수국과 비교하여 낮은 것은 줄기의 세포 구조상 방사조직의 형태, 섬유세포의 밀도, 도관의 발달, 전분 함유 세포의 수 등에 차이가 관찰되 었고 이러한 세포 구조적 차이들의 영향으로 나무수국이 수국 보다 삽목 후 뿌리 조직 세포분열이 7일 늦게 시작되는 것이 확인되었다. 본 연구의 결과로 나무수국의 삽목 번식의 기초 자료로 활용되어 묘목 생산 효율 증대에 활용되길 바란다.

메타버스는 탐험, 사회적 상호 작용, 창의적 표현이 가능한 오픈 월드를 특성으로 하며, 대표적인 메타버스 플랫폼인 로블록스는 십대에게 다양한 게임을 제공하고 있다. 십대 청소년은 엔터테인먼트뿐만 아니라 커뮤 니케이션, 가상 구매, 일탈을 위해 게임에 참여한다. 이에 따라 십대 유저와 아바타 간의 관계를 연구는 계속 되었다. 본 연구는 러시아 십대 유저를 대상으로 로블록스 플레이어의 게임 동기와 아바타의 동기화 사이의 연관성을 조사한다. 본 논문을 위해 러시아 십대 청소년 133명을 대상으로 게임 동기와 아바타 동기화 부문 에 대한 20개의 문항으로 구성된 온라인 설문조사를 실시했다. 그 결과 게임 동기와 아바타 동기화 사이에 상관관계가 나타났다. 일례로 일탈을 위해 로블록스를 하는 유저는 아바타를 자신(아바타-나)과 같다고 인식 하는 것으로 나타났으며, 사회적 동기를 갖고 로블록스를 즐기는 유저는 아바타를 하나의 도구로 인식하는 것으로 나타났다. 아바타를 '나'로 인식하는 것은 모든 게임 동기와 상관관계가 있는 것으로 나타났다. 또한 본 논문의 연구 결과는 아바타의 외형이 아바타 동기화와 높은 관련이 있다는 것을 보여주었다. 유저가 아바 타를 어떻게 인식하는 지를 이해하는 것은 메타버스 내에서 보다 안전하고 사용자 친화적인 온라인 환경을 조성하고 더 많은 플레이어를 끌어들이는 데 있어서 매우 중요한 요소임을 확인하였다.

Recently, China has published the “Security Assessment Measures for Outbound Data Transfers,” a crucial regulation on outbound data flows. This regulation contains strong national security considerations and produces independent and direct legal effects compared with other assessment systems in China’s laws. However, there is a possibility that conflict arises between these measures and the international commitments made by China due to the ambiguity in how "critical data" is defined, the excessive emphasis placed on self-risk assessment, and the arbitrary extension of procedures. Particularly, with China's current application to join the CPTPP, the restrictive measures of its cross-border data flow may appear to violate the obligation of CPTPP, but may be justified through CPTPP’s exception clauses. In light of this, it is necessary for China to adopt a more modest approach to balancing data security with the effort made to promote the flow of cross-border data.

This study explores the impact of metal doping on the surface structure of spent nuclear fuels (SNFs), particularly uranium dioxide (UO2). SNFs undergo significant microstructural changes during irradiation, affecting their physical and chemical properties. Certain elements, including actinides and lanthanides, can integrate into the UO2 lattice, leading to non-stoichiometry based on their oxidation state and environmental conditions. These modifications are closely linked to phenomena like corrosion and oxidation of UO2, making it essential to thoroughly characterize SNFs influenced by specific element doping for disposal or interim storage decisions. The research employs X-ray diffraction (XRD), scanning electron microscopy (SEM), and Raman spectroscopy to investigate the surface structure of UO2 samples doped with elements such as Nd3+, Gd3+, Zr4+, Th4+, and ε-particles (Mo, Ru, Pd). To manufacture these samples, UO2 powders are mixed and pelletized with the respective dopant oxide powders. The resulting pellet samples are sintered under specific conditions. The XRD analysis reveals that the lattice parameters of (U,Nd)O2, (U,Gd)O2, (U,Zr)O2, and (U,Th)O2 linearly vary with increasing doping levels, suggesting the formation of solid solutions. SEM images show that the grain size decreases with higher doping levels in (U,Gd)O2, (U,Nd)O2, and (U,Zr)O2, while the change is less pronounced in (U,Th)O2. Raman spectroscopy uncovers that U0.9Gd0.1O2-x and U0.9Nd0.1O2-x exhibit defect structures related to oxygen vacancies, induced by trivalent elements replacing U4+, distorting the UO2 lattice. In contrast, U0.9Zr0.1O2 shows no oxygen vacancy-related defects but features a distinct peak, likely indicating the formation of a ZrO8-type complex within the UO2 lattice. ε-Particle doped uranium dioxide shows minimal deviations in surface properties compared to pure UO2. This structural characterization of metal-doped and ε-particle-doped UO2 enhances our understanding of spent nuclear fuel behavior, with implications for the characterization of radioactive materials. This research provides valuable insights into how specific element doping affects the properties of SNFs, which is crucial for managing and disposing of these materials safely.

Noble metal phase, present in used fuel, are fission products that can be found as metallic precipitates in used nuclear fuel. They exist as small particles (nm~um) in grain boundaries of the used fuels. Since they are particles deposited between the grain structures, they can be considered as defects in the pellet structure. Thermal expansion of fuels with noble metal is slightly higher than that of bare fuels. The fuels at high temperature, such as immediately after being discharged from nuclear reactors, may be subject to fuel failure if sufficient cooling is not provided. Recent research has shown that the noble metals can migrate into the rim space between the pellet and the cladding, and be deposited in the inner layer of the claddings. therefore, the mechanical integrity of the cladding can be degraded by noble metals, as well as the pellets. The concentration of the noble metal phase should be considered to evaluate the effect of the noble metals on the fuel integrity, after discharge from the reactors. SCALE/ORIGEN code was used to evaluate the noble metals in fuel assembly-scale, and the radial distribution in the fuel assembly. The radial distribution of the reactor power was derived from the SCALE/TRITON, considering Westinghouse 17×17. Square cell model was chosen for the geometry and 1/4 model was applied to reduce the computation time.

Most of the C-14 produced is in the organic form, generated as methane (14CH4), methanol (14CH3OH), formaldehyde (14CH2O), and formic acid (14CO2H2). When analyzing C-14, it is transformed into the form of 14CO2, and its concentration is determined using LSC. Typical examples include the wet oxidation method, the combustion or Pyrolysis. The wet oxidation method uses strong acids and involves repeated operations, which generates large amounts of acid waste and secondary radioactive waste. The combustion method uses high temperatures, which requires an oxygen device. Pyrolysis also requires high temperature in a vacuum and catalysts. Catalysts are expensive because they are platinum-based. To compensate for these shortcomings, a C-14 analysis method using UV irradiation was developed. In this study, 100 mL of distilled water mixed with formic acid (CO2H2), potassium persulfate (K2S2O8), and silver nitrate (AgNO3) was irradiated with a 320-390 nm UV lamp to conduct a CO2 production reaction experiment. The UV range was measured using a photometer (UV Power puck II). The beaker was made of quartz in 150 mL size with three inlets : a temperature measurement, a sample inlet, and a collection tube connector. We changed the UV lamp used from a 450 W halogen lamp to a 100 W LED, which has a lower temperature and is safer. As a result of the experiment, CO2 bubbles were generated in the collection tube, due to the UV irradiation react, which uses oxidizer and catalysts. The maximum temperature of the solution irradiated with the LED UV lamp was less than 56°C. It confirmed the rate of bubble generation changed depending on the lamp distance, the amount of sample, oxidizer, and catalyst. In an experiment to confirm the reaction caused by heat, it was found that although a reaction occurred due to heat, the reaction was significantly lower than when using a UV lamp. The reproducibility experiment was conducted three times in total under the same conditions. It showed the same pattern. In the future, we plan to select mock samples, collect 14CO2 in Carbo- Sorb, and analyze them using LSC. The results of this research will be used as a technology to recover C-14 more safely and efficiently and will also be used to expand its application to the treatment of other wastes such as waste liquid and waste resin through simulated samples.

This study presents distribution of naturally occurring radioactive materials in groundwater in Jeju island. Radon (222Rn) and potassium (40K) concentrations were performed by using Liquid Scintillation Counter and Ion Chromatograph respectively. In addition, the activities of uranium and thorium nuclides were analyzed by Inductively Coupled Plasma Mass Spectroscopy. Groundwater samples were collected from 9 sites of water intake facilities for wide area supply in Jeju island from September 2022 to September 2023. The 40K concentrations of groundwater ranged between 0.050 and 0.400 Bq·L-1. The radon concentrations in groundwater were in the range of 0 to 60 Bq L-1, and there was no groundwater exceeding the range of 148 Bq L-1 proposed by the US EPA. The distribution of uranium and thorium in groundwater varied from 0 to 500 ng L-1 and 0 to 2.4 ng L-1, respectively. The concentrations of uranium did not exceed 30 μg L-1, thresholds indicated by the US EPA. By analyzing the concentrations of 40K, 222Rn, 238U and 232Th, the annual effective dose of residents can be assessed. The evaluated residents’ effective dose from natural radionuclides due to intake of drinking water is less than the recommended value of 100 μSv y-1. Consequently, this study indicates that the cancer risks of the residents in Jeju island from naturally occurring radioactive materials ingested with water is insignificant.

The radiological characterization of SSCs (Structure, Systems and Components) plays one of the most important role for the decommissioning of KORI Unit-1 during the preparation periods. Generally, a regulatory body and laws relating to the decommissioning focus on the separation and appropriate disposal or storage of radiological waste including ILW (intermediate level waste), LLW (low level waste), VLLW (very low level waste) and CW (clearance waste), aligned with their contamination characteristics. The result of the preliminary radiological characterization of KORI Unit-1 indicated that, apart from neutron activated the RV (reactor vessel), RVI (reactor vessel internals), and BS (biological shielding concrete), the majorities of contamination were sorted to be less than LLW. Radiological contamination can be evaluated into two methods. Due to the difficulties of directly measuring contamination on the interior surfaces of the pipe, called CRUD, the assessment was implemented by modeling method, that is measuring contamination on the exterior surfaces of the pipes and calculating relative factors such as thickness and size. This indirect method may be affected by the surrounding radiation distribution, and only a few gamma nuclides can be measured. Therefore, it has limitation in terms of providing detailed nuclide information. Especially, α and β nuclides can only be estimated roughly by scaling factors, comparing their relative ratios with the existing gamma results. To overcome the limitation of indirect measurement, a destructive sampling method has been employed to assess the contamination of the systems and component. Samples are physically taken some parts of the systems or components and subsequently analyzed in the laboratory to evaluate detailed nuclides and total contamination. For the characterization of KORI Unit-1, we conducted the radiation measurement on the exterior surfaces of components using portable instruments (Eberline E-600 SPA3, Thermo G20-10, Thermo G10, Thermo FH40TG) at BR (boron recycle system) and SP (containment spray system) in primary system. Based on these results, the ProUCL program was employed to determine the destructive sample collection quantities based on statistical approach. The total of 5 and 8 destructive sample quantities were decided by program and successfully collected from the BR and SP systems, respectively. Samples were moved to laboratory and analyzed for the detail nuclide characteristics. The outcomes of this study are expected to serve as valuable information for estimating the types and quantities of radiological waste generated by decommissioning of KORI Unit-1.