Domestic commercial low- and intermediate-level radioactive waste storage containers are manufactured using 1.2 mm thick cold-rolled steel sheets, and the outer surface is coated with a thin layer of primer of 10~36 μm. However, the outer surface of the primer of the container may be damaged due to physical friction, such as acceleration, resonance, and vibration during transportation. As a result, exposed steel surfaces undergo accelerated corrosion, reducing the overall durability of the container. The integrity of storage containers is directly related to the safety of workers. Therefore, the development of storage containers with enhanced durability is necessary. This paper provides an analysis of mechanical properties related to the durability of WC (tungsten carbide)-based coating materials for developing low- and intermediate-level radioactive waste storage containers. Three different WC-based coating specimens with varied composition ratios were prepared using HVOF (high-velocity oxy-fuel) technique. These different specimens (namely WC-85, WC-73, and WC-66) were uniformly deposited on cold-rolled steel surfaces ensuring a constant thickness of 250 μm. In this work, the mechanical properties of the three different WCbased coaitng materials evaluated from the viewpoints of microstructure, hardness, adheision force between substrate and coating material, and wear resistance. The cross-sectional SEM-EDS (Scanning Electron Microscope-Energy Dispersive X-ray Spectroscopy) images revealed that elements W (tungsten), C (carbon), Ni (nickel), and Cr (chromium) were uniformly distributed within the each coating layers which was approximately 250 μm thick. The average hardness values of HWC-85 and HWC-73 were found to be 1,091 Hv (Vickers Hardness) and 1,083 Hv, respectively, while the HWC-66 exhibited relatively lower hardness value of 883 Hv. This indicates that a higher WC content results in increased hardness. Adhesion force between and substrates and coating materials exceeded 60 MPa for all specimens, however, there were no significant differences observed based on the tungsten carbide content. Furthermore, a taber-type abrasion tester was used for conducting abrasion resistance tests under specific conditions including an H-18 load weight at 1,000 g with rotational speed set at 60 RPM. The abrasion resistance tests were performed under ambient temperatures (RT: 23±2°C) as well as relative humidity levels (RH: 50±10%). Currently, the ongoing abrasion resistance tests will include some results in this study.

This study focuses on the development of coatings designed for storage containers used in the management of radioactive waste. The primary objective is to enhance the shielding performance of these containers against either gamma or neutron radiation. Shielding against these types of radiation is essential to ensure the safety of personnel and the environment. In this study, tungsten and boron cabide coating specimens were manufactured using the HVOF (High-Velocity Oxy Fuel) technuqe. These coatings act as an additional layer of protection for the storage containers, effectively absorbing and attenuating gamma and neutron radiation. The fabricated tungsten and boron carbide coating specimens were evaluated using two different testing methods. The first experiment evaluates the effectiveness of a radiation shielding coating on cold-rolled steel surfaces, achieved by applying a mixture of WC (Tungsten Carbide) powders. WC-based coating specimens, featuring different ratios, were prepared and preliminarily assessed for their radiation shielding capabilities. In the gamma-ray shielding test, Cs-137 was utilized as the radiation source. The coating thickness remained constant at 250 μm. Based on the test results, the attenuation ratio and shielding rate for each coated specimen were calculated. It was observed that the gammaray shielding rate exhibited relatively higher shielding performance as the WC content increased. This observation aligns with our findings from the gamma-ray shielding test and underscores the potential benefits of increasing the tungsten content in the coating. In the second experiment, a neutron shielding material was created by applying a 100 μm-thick layer of B4C (Boron Carbide) onto 316SS. The thermal neutron (AmBe) shielding test results demonstrated an approximate shielding rate of 27%. The thermal neutron shielding rate was confirmed to exceed 99.9% in the 1.5 cm thick SiC+B4C bulk plate. This indicates a significant reduction in required volume. This study establishes that these coatings enhance the gamma-ray and neutron shielding effectiveness of storage containers designed for managing radioactive waste. In the future, we plan to conduct a comparative evaluation of the radiation shielding properties to optimize the coating conditions and ensure optimal shielding effectiveness.

We fabricated dual-phase free-standing polymeric membrane for high performance CO2/N2 separation, introducing amphiphilic, CO2-philic copolymer via one-step free radical polymerization, or (2-[3-(2H-benzotriazol-2-yl)-4-hydroxyphenyl]ethyl methacrylate)-graft-poly(oxyethylene methacrylate) (PBE). PBE filler partially interacts with Pebax polymer matrix to generate the interconnected CO2 philic network, exhibiting a microphase-separated, or dual-phase behavior in Pebax matrix. The performance of CO2/N2 separation was increased according to the PBE content, with the maximum selectivity at 5 wt%. The enhancement of Pebax/PBE CO2-philic membrane was attributed to the formation of CO2-philic channel consisting of ether oxygens and triazole groups. The best performance was CO2 permeability of 175.3 Barrer and CO2/N2 selectivity of 48.2.

PVC-g-POEM graft copolymer was synthesized for ultrafiltration (UF) membrane area and the effect of TTIP on the membranes was also explored via phase separation. Characterization was explored by FT-IR, 1H-NMR and FE-SEM and measured by cross-flow system. The interaction between copolymer and TTIP enhanced the water permeance because of increased surface pore size and porosity. Phase inversion process in 80 oC water bath resulted in decreased water permeance owing to the increased top selective layer, but increased BSA rejection. However, TTIP-treated membrane with 80 oC inversion showed decreased BSA rejection owing to TTIP dissolution in hot water. TTIP treatment and 80 oC inversion resulted in highly enhanced antifouling property. The best performance exhibited 338 LMH water permeance, 89.4% BSA rejection, and 91.9% flux ratio recovery.

메조포러스 공극구조를 갖는 광촉매 멤브레인은 다양한 환경기술에 적용될 수 있다. 본 연구에서는 TiO2 층을 형 성시킨 광촉매 반응기용 세라믹 멤브레인을 개발하고 이를 염색용액 처리에 적용하였다. 높은 공극률과 균질성을 지닌 TiO2 광촉매층을 그라프트 공중합체를 사용하여 제조하였다. 멤브레인은 광촉매 반응기와 멤브레인 여과를 결합시킨 하이브리드 광촉매 반응기에 성공적으로 적용하였다. 실험결과 정렬된 구조의 TiO2 층이 Al2O3 지지체에 형성되었다. TiO2 층 형성 후 제조된 세라믹 분리막의 순수 투과도는 형성된 광촉매 층 저항으로 감소하였다. 정렬된 구조의 TiO2 층은 UV 결합 시 5시간 안에 완벽한 염색용액 분해를 달성시킬 수 있었다. 광촉매 멤브레인의 염색용액 분해는 Langmuir-Hinshelwood 흡착 모델로 잘 설명할 수 있었다. 또한 TiO2 층이 고정화된 세라믹 멤브레인의 model Congo Red에 대한 1차 속도상수는 Al2O3 지지체 단독인 경우에 비해 약 6배 정도 큰 값을 나타내었다(0.0081 vs. 0.0013 min-1).

In the electronic device area, several conductive polymers have been used such as Poly(3,4-ethylenedioxythiophene) polystyrene sulfonate (PEDOT-PSS). In the connection of this concept, PEDOT-PSS was applied to CO2/N2 separation, which is the first attempt to this area. To be specific, the polymer was blended to poly(2-[3-(2H- benzotriazol-2- yl)-4-hydroxyphenyl] ethyl methacrylate)-poly(oxyethylene methacrylate) (PBEM-POEM or PBE). The conductive polymer formed the interconnected network by interacting with PBE owing to the specific interaction. This structure give the facile pathway to CO2 and N2, which result in the increased permeability of the gases. Especially, improved CO2 solubility caused the permeability (59.6 Barrer) to be increased, which brought about the enhanced CO2/N2 selectivity (77.4) of PEDOT-PSS 5 wt% membrane.

TiO2 and SiO2 inorganic nanoparticles were synthesized with poly(oxyethylene methacrylate)(POEM) and blended with 1-methyl-3-propylimidazolium iodide(MPII), poly(ethylene glycol)(PEG), and iodine(I2) to prepare polymer electrolyte membranes for dye-sensitized solar cells(DSSC). The modified nanoparticles were prepared by the grafting of POEM to TiO2 and SiO2 nanoparticles and put into PEG, MPII and I2 to produce polymer electrolyte membranes. The specific interactions of PEG with the modified nanoparticles in addition to ionic liquid were confirmed by FT-IR spectroscopy and DSC, providing gel formation of electrolytes. The efficiency of DSSC employing TiO2-POEM/PEG/MPII/I2(3.3%) was slightly higher than that employing SiO2-POEM/PEG/MPII/I2(2.9%) due to the different ionic conductivity of electrolytes membrane.

[6]-Gingerol, a major polyphenol of ginger(Zingiber officinale), exhibits a variety ofbiological properties including anti-oxidant, anti-inflammatory and anti-cancer activity. However,the radioprotective effect of [6]-gingerol is still unknown. The aim of this study was to investigatethe radioprotective effect of [6]-gingerol against radiation-induced cell cytotoxicity and oxidativestress in HepG2 cells. [6]-Gingerol pretreatment attenuated radiation-induced cell cytotoxicitycaused by 5Gy(half lethal dose, LD50of HepG2 cells). The measurements of superoxide dismutase(SOD) and catalase(CAT) activity were also performed. The results showed that [6]-gingerol pre-treatment reduced increasing SOD and CAT activity after exposure of IR, indicating that [6]-gin-gerol protected oxidative stress by regulating cellular antioxidant enzyme(SOD and CAT) activity.These findings suggest that [6]-gingerol acts as a radioprotector by attenuating cell cytotoxicityand oxidative stress.

Microbial fermented cellulose gel, citrus gel(CG), was successfully fabricated to porousfoam by radiation treatment and freeze drying. The chemically induced radiation was used to createhighly porous foam and further freeze drying of the CG produced tough foams with interconnectedopen pores for use in tissue engineering. The microstructure of the CG foam was controlled byvarying the irradiation dose and quenching temperature with pore size ranging from several micronsto a few hundred microns. Tensile strength and Gurley value of the CG foam were influenced byirradiation dose. These radiation induced CG foams are promising scaffolds for tissue engineering.

Opioid receptors have been pharmacologically classified as µ, δ, κ and ε. We have recently reported that the antinociceptive effect of morphine (a µ-opioid receptor agonist), but not that of β-endorphin (a novel µ/ε-opioid receptor agonist), is attenuated by whole body irradiation (WBI). It is unclear at present whether WBI has differential effects on the antinociceptive effects of µ-, δ-, κ- and ε-opioid receptor agonists. In our current experiments, male ICR mice were exposed to WBI (5Gy) from a 60 Co gamma-source and the antinociceptive effects of opioid receptor agonists were assessed two hours later using the hot water (52℃) tail-immersion test. Morphine and D-Ala2,N-Me-Phe4,Gly-ol-enkephalin (DAMGO), [D-Pen2-D-Pen5]enkephalin (DPDPE), trans-3,4-Dichloro-N-methyl-N-[2-(1-pyrrolidinyl)- cyclohexyl]¬benzeneacetamide (U50,488H), and β-endorphin were tested as agonists for µ, δ, κ, and ε-opioid receptors, respectively. WBI significantly attenuated the antinociceptive effects of morphine and DAMGO, but increased those of β-endorphin. The antinociceptive effects of DPDPE and U50,488H were not affected by WBI. In addition, to more preciously understand the differential effects of WBI on µ- and ε¬opioid receptor agonists, we assessed pretreatment effects of β-funaltrexamine (β-FNA, a µ-opioid receptor antagonist) or β-endorphin1-27 (β-EP1-27, an ε-opioid receptor antagonist), and found that pretreatment with β-FNA significantly attenuated the antinociceptive effects of morphine and β endorphin by WBI. significantly reversed the β-EP1-27 attenuation of morphine by WBI and significantly attenuated the increased effects of β-endorphin by WBI. The results demonstrate differential sensitivities of opioid receptors to WBI, especially for µ- and ε-opioid receptors.

Poly(vinyl chloride)-g-poly(styrene sulfonic acid) (PVC-g-PSSA) 가지형 공중합체를 합성한 후, 이를 이용하여 80℃에서 열적으로 환원하여 은 나노입자를 제조하였다. 반응 시간을 바꿈에 따라 다양한 구조의 은 나노입자를 제조하는데 성공하였다. 1시간 정도의 짧은 반응 시간에서는 가지형 공중합체의 미세 상분리 구조를 크게 변화시키지 않고 5 nm 크기의 작은 은 나노입자가 생성되었다. 5시간 정도의 중간 반응 시간에서는 30 내지 50 nm 정도의 크기를 갖는 은 나노입자가 생성되었다. 18시간 정도의 긴 반응 시간에서는, 은입자가 뭉친 허리케인 모양의 은 집합체가 관찰되었다.

Radioprotection is of practical importance for the normal tissues of tumor patients subject to radiotherapy, people with planned or accidental exposure to radiation, and the public and radiation workers. Since oxygen enhances radiation - induced biologica