To analyze the activity concentration of radionuclides in radioactive sludge samples generated from low- and intermediate-low-level radioactive waste from domestic nuclear power plant, a pretreatment process that dissolves and homogenizes the sample is essential. However, this pretreatment process requires the use of hydrofluoric acid, which makes analysis difficult and challenges users to handle harmful chemicals. Therefore, we aim to minimize the use of hydrofluoric acid by measuring gamma nuclides in the sludge sample without pretreatment process and compare the differences of measurement results according to the sample matrix with and without pretreatment process. We will collect about 0.1 g of the sludge sample, and dissolve it using an acid treatment process after using microwave decomposition. We will then use gamma spectroscopy to check the concentration of nuclides present in the sludge before and after dissolution and consider the effect of the sample matrix.

본 연구에서는 PEBAX 2533에 합성된 PEI-GO@ZIF-8의 함량을 달리 첨가하여 혼합막을 제조하고 N2와 CO2의 투과 특성을 연구하였다. PEBAX/PEI-GO@ZIF-8 혼합막의 N2 투과도는 PEI-GO@ZIF-8 함량이 증가함에 따라 감소하였고, CO2 투과도는 PEI-GO@ZIF-8 함량에 따라 다른 경향을 보였는데 순수 PEBAX 막에서 PEI-GO@ZIF-8 0.1 wt%까지 CO2 투과도는 증가하다가 그 이후의 함량에서는 감소하였다. PEI-GO@ZIF-8 0.1 wt% 혼합막은 CO2 투과도 221.9 Barrer, CO2/N2 선택도는 60.0으로, 제조된 혼합막들 중 CO2 투과도와 CO2/N2 선택도가 향상되어 가장 높은 투과 특성을 보였고 Robeson upper-bound에 도달하는 결과를 얻었다. 이는 충진물이 PEBAX 내에 고루 분산되면서 CO2와 친화적인 상호작용을 하는 GO의 -COOH, -O-, -OH 작용기와 PEI에 결합된 아민기 그리고 CO2에 대해 gate-opening 현상이 일어나는 ZIF-8의 영 향 때문이다.

Interest in the use of semiconductor-based photocatalyst materials for the degradation of organic pollutants in a liquid phase has grown, due to their excellent performance and response to the light source. Herein, we fabricated a NiO-SiCTiO2 ternary structured photocatalyst which had reduced bandgap energy, with strong activation under UV-light irradiation. The synthesized samples were examined using XRD, SEM, EDX, TEM, DRS, EIS techniques and photocurrent measurement. The results confirmed that the two types of metal oxides were well bonded to the SiC fiber surface. The junction of the new photocatalyst exhibited a large number of photoexcited electrons and holes. The holes tended to oxidize the water and form a hydroxyl radical, which promoted the decomposition of methylene blue. The close contact between the 2D SiC fiber and metal oxide semiconductors expanded the scope of absorption wavelength, and enhanced the usability of the ternary photocatalyst for the degradation of methylene blue. Among three synthesized samples, the NiO-SiC-TiO2 showed the best photocatalytic effect, and was considered to have excellent photoelectron transfer due to the synergy effect between the metal oxide and SiC.

본 연구에서는 zeolitic imidazolate framework-9 (ZIF-9)을 합성하고 poly(ether-b-amide)-1657 (Pebax-1657) 내에 함량을 달리하여 Pebax/ZIF-9 혼합막을 제조한 다음 단일기체 (N2, CO2)를 투과하여 혼합막에 대한 기체 투과 특성을 조사하 였다. 순수 Pebax 막 내에 혼입되는 ZIF-9 함량이 증가함에 따라 N2 투과도는 점차 감소하고, CO2 투과도는 Pebax/ZIF-9 3 wt% 혼합막까지 증가하다가 그 이후의 함량에서는 감소하였다. 그리고 혼합막들 중 Pebax/ZIF-9 3 wt% 혼합막은 극성 기체 인 CO2에 대해 gate-opening 현상이 일어나면서 선택적으로 CO2를 받아들여 가장 높은 선택도 69.3을 보였다. 또한 CO2 투 과도와 CO2/N2 선택도가 모두 증가하여 Robeson upper-bound에 가장 근접하는 결과를 얻었다.

The Korean administration assumed that the amount of low and medium level waste generated during the decommissioning of nuclear facilities in Korea was 14,500 drums (based on 200 L) and designed the LILW repository accordingly. Accordingly, it is necessary to separate the nuclear power plant decommissioning waste into clearance waste by mobilizing means such as decontamination and cutting as much as possible, and to deregulate it together with non-radioactive waste. As a result, clearance waste and non-radioactive waste are dominated by concrete and metal, and it is necessary to evaluate how to recycle them. Many existing studies have conducted research on each recycling method, and accordingly, it can be judged that the technological maturity is sufficient. Accordingly, we would like to propose a method for comprehensive management and evaluation of concrete. By applying the decision matrix proposed in IAEA TRS No. 401, it will be possible to compare the 5 factors (cost, technical feasibility, risk, availability of disposal, and full cycle impact). However, in the case of concrete, if the existing construction waste recycling methodologies are fully used, the technical feasibility can be considered equal. Therefore, it was judged that it would be good to introduce the aspect of public acceptance as an evaluation item instead of technical feasibility. The amount of waste that can be generated when decommission a nuclear power plant is only insignificant compared to the total amount of waste concrete that is generated during the year. Accordingly, one option is to fully integrate the waste concrete recycling system and utilize it for road construction. Next, it is possible to suggest the option of recycling in the construction of shields in the nuclear industry, as suggested in previous studies, and the method of using it as a backfill material such as for a decommissioned NPP site or other sites. As an example, and a draft stage, this study was evaluated based on existing studies after all options were equally weighted. When the profit and loss was evaluated in a way that a maximum of 5 points were given to each option, the case of using it as a backfill in various applications was evaluated as the best option. Unlimited recycling, such as road construction, was evaluated to be highly damaging in terms of public acceptance.