During the larval development process of insects, juvenile hormone (JH) is essential for regulating various aspects of larval life, including growth, reproduction, and behavior, throughout their larval stage. The larval stage of Spodoptera frugiperda, when it consumes plant-derived metabolites, develops into pupae, but these pupae are unable to molt successfully. In this way, plant-derived metabolites contain or produce inhibitors of juvenile hormone, thereby disrupting the development of insect larvae and making them vulnerable to harm. Therefore, in this study, we established an in vitro screening system using yeast cells transformed with the Met-SRC juvenile hormone receptor of S. frugiperda. Through this system, we were able to identify juvenile hormone disruptors from plant-derived metabolites and confirm their developmental inhibitory effects on the larvae of S. frugiperda.

본 연구에서는 경기도내 유통되고 있는 심해성 어류 50 건을 대상으로 수은, 메틸수은의 오염도 및 셀레늄의 함 량을 알아보았다. 금아말감법의 수은분석기, ICP-MS를 사 용하여 측정하였으며 각 항목별 평균함량은 수은 0.7647 mg/ kg (0.0182-5.3620), 메틸수은 0.0764 mg/kg (0.0096-0.8750), 셀레늄 0.4728 mg/kg(0.1075-3.5100)으로 메틸수은은 50건 모두 기준규격(1.0 mg/kg) 이하로 나타났다. 셀레늄은 수 은과 결합하여 수은의 독성을 감소시키는 것으로 알려져 있으며, 본 연구과제에서는 일일평균섭취량이 3.3 μg/kg으 로 일일권장량보다 낮은 수치였다. 유해물질인 수은과 메 틸수은은 JECFA에서 설정한 PTWI의 5.7%, 1.8%로 조사 되었다. 따라서 도내에서 유통되는 심해성 어류의 수은, 메틸수은과 같은 위해중금속은 안전한 것으로 나타났지만 지속적 모니터링이 필요하다고 판단된다.

The concrete structure of a nuclear power plant is a major safety structure that performs shielding functions to block radioactive materials and radiation, heat removal, and isolation functions. Therefore, concrete structures of nuclear power plants must prove structural safety from immediately after construction to dismantling, and a representative method for this is to investigate compressive strength. The compressive strength and specimen standards of concrete structures are specified in ASTM C 42/C 42M, and samples must be obtained through core drilling in order to collect samples according to this standard. However, commercial equipment requires anchor installation work causes radiation dust generation. Even commercial products have developed equipment that does not require anchor installation work, but it can only be applied to flat walls and cannot be applied to curved walls such as bioshields. To solve this problem, a method of fixing to the scaffolding pipe was designed. The equipment developed based on this method fundamentally blocks the generation of radioactive dust. The vertical position can be adjusted using guide shafts and jack screws, and the horizontal position can be adjusted using scaffolding clamps. In addition, the distance between the installation location and the wall can be adjusted by adjusting the scaffolding clamp location of the device. Lastly, it can be rotated to the left and right, so that even on a curved wall, the sampling position can be performed perpendicular to the wall. Core drills that take specimens for measuring compressive strength use the wet type. Core drilling by wet type in radioactively contaminated concrete leads to the disposal of sludge as radioactive waste. Water supplied during core drilling is scattered in all directions by the rotation of the core drill bit, which causes radiation exposure to workers, so measures must be taken to ensure that the water does not splash and gather in one place. Nileplant Co., Ltd. has developed a sludge collection device that can be used with a core drilling device. It can be inserted into a 4-inch core drill bit to meet the specimen regulations of ASTM C 42/C 42M, and nylon resin was used as a material to withstand friction with water, and the wall of the drainage part was thickened to increase durability. Based on these results, it is expected to be able to work more quickly and safely when collecting core drilling samples of radioactively contaminated concrete or radiation and concrete.

Various types of tanks are used in nuclear power plants, and sludge composed of various organic substances and inorganic oxides contaminated with radioactive materials may be present at the bottom of a tank of a radioactive waste treatment device. In addition, glassy and fixative oxide contamination layers are accumulated on the inner wall of the tank depending on the tank material, usage and degree of oxidation. Such contaminated sludge is the main cause of radiation exposure to workers when dismantling nuclear power plant tanks. In addition, the waste filters generated by filtration of contaminated sludge is treated as secondary radioactive waste, and this radioactive waste not only occupies a lot of disposal space, but also the disposal cost is continuously increasing. Therefore, it is necessary to develop a technology that does not generate waste filters as much as possible. To solve this problem, NILEPLANT Co., Ltd. registered a patent named “Filtering apparatus” based on previous research and manufactured a rotary filtration membrane device through detailed design. The rotary filtration membrane device is composed of three or more multiple rotary filtration membranes, and can remove fine particles in wastewater as well as sludge accumulated inside a radioactive contamination tank. In addition, considering the site characteristics of special conditions such as nuclear power plants, it was designed to show excellent performance in removing fine particles while minimizing the area where the device is installed. The rotary filtration membrane device is designed and manufactured as a double cylinder structure that combines a hydro cyclone filter type body and an inner partition wall, and is equipped with a filter cloth-based rotary cylinder filter to process sludge through the filter cloth in addition to inertial. In addition, the patented principle enables self-backwashing without stopping the filtration process, extending the life of the filter and minimizing waste filters. The filtration performance, self-backwashing function, and sludge behavior of the rotary filtration membrane device manufactured based on the detailed design were evaluated through experiments, and improvements to obtain more effective filtration performance were derived. Accordingly, it is expected that the more improved rotary filtration membrane device can be effectively used to remove sludge generated during the dismantling of nuclear power plants in the future.

In this study, heavy metals (lead, cadmium, and mercury) and shellfish poisoning toxins (diarrhetic shellfish poisoning toxins, amnesic shellfish poisoning toxins) were investigated in a total of 104 shellfishes. According to the analysis of heavy metals, lead (Pb) was detected in the range of 0.0177-0.5709 mg/kg, cadmium (Cd) was detected in the range of 0.0226-1.4602 mg/kg, and mercury (Hg) was detected in the range of 0.0015-0.0327 mg/kg. Levels of Pb, Cd, and Hg were acceptable by Korean standards. Okadaic acid (OA) and dinophysistoxin-1 (DTX-1) were investigated for monitoring of diarrhetic shellfish poisoning toxins and OA and DTX-1 were not detected. As a result of monitoring of amnesic shellfish poisoning toxins, domoic acid was detected in 5 of 104 samples and detection ratio was 4.8%. The detection period was found as follows; 1 case in January, 1 case in February, 1 case in May, 2 cases in September. These showed that continuous monitoring for the management of shellfish poisoning toxins and heavy metals is required. In addition, this study can be used as reference data to strengthen managing heavy metals in fishery products.

본 연구는 견과종실류 및 그 가공품을 대상으로 LC/MS/ MS를 이용하여 aflatoxin (B1, B2, G1, G2), ochratoxin A, fumonisin (B1, B2), zearalenone을 동시 분석하여 오염 실태를 조사하였다. 연구 대상 106건 중 37건(35%)에서 곰팡이독소가 검출되었으며, 2항목 이상의 곰팡이독소가 동시에 검출된 경우는 8.5%로 조사되었다. Aflatoxin, ochratoxin A, fumonisin, zearalenone은 각각 0.08-1.45 μg/ kg, 17.29 μg/kg, 1.16-14.89 μg/kg, 0.12-12.69 μg/kg의 농도 범위로 검출되었다. 검출 빈도로 보면 zearalenone (23%), aflatoxin (13%), fumonisin (8%), ochratoxin A (1%) 순으로 높은 검출율을 보였다. 원물 형태인 견과류와 유지종 실류는 각각 35%, 33%의 검출율을 나타내었고 이를 가공한 견과류가공품과 유지종실류가공품은 각각 44%, 46% 의 검출율을 나타내어 가공 식품에서의 곰팡이독소 검출율이 10% 이상 높게 나타났다. 곰팡이독소는 물리화학적으로 안정한 물질로서 가공이나 조리 과정 중에도 그대로 남아있어 식품 원료에서의 곰팡이독소 관리가 더 중요할 것으로 판단된다.

간편식 형태의 이유식 중 죽 44건, 진밥 40건, 퓌레 11 건, 분말 6건으로 총 101건의 무기질(철, 아연, 칼슘, 마그네슘) 함량을 마이크로웨이브 분해장치로 분해하여 ICPOES로 분석하였다. 무기질의 유형별 평균 함량은 철 0.05- 0.45 mg/100 g(mg/10 g, 분말), 아연 0.06-0.29 mg/100 g(mg/ 10 g, 분말), 칼슘 3.07-6.65 mg/100 g(mg/10 g, 분말), 마그네슘 2.46-5.93 mg/100 g(mg/10 g, 분말)으로 나타났다. 철, 아연, 칼슘, 마그네슘의 권장섭취량(KDRIs)과 비교하였을 때 권장섭취량 대비 각각 2.74-22.35%(평균 11.10%), 5.94- 28.95%(평균 21.91%), 3.07-6.65%(평균 4.47%), 13.42-38.95% (평균 22.85%)이었다. 시판되는 간편 이유식만으로는 생후 6개월 이후 각각의 무기질 권장섭취량을 충분히 섭취할 수 없어 조제식이나 모유를 통한 영양소 섭취가 필요하다. 충분한 무기질 섭취를 위해서는 각각 영양소의 주요 급원 식품을 파악하고 부족한 영양소를 섭취할 수 있는 간편 이유식을 선택하는 것을 권장한다. 아울러 제조회사에서 는 우리나라 영유아시기에 부족해지기 쉬운 철, 칼슘 등 의 영양소를 강화한 재료를 이유식 제조에 사용·표기하여 영유아의 성장발달에 필요한 영양소가 균형 있게 공급될 수 있도록 해야 할 것이다.

This study constructed a wheat-specific primer and a probe using the internal transcribed spacer (ITS). 2 regions of wheat (Triticum aestivum) and real-time PCR conditions were established. The calibration curve showed a slope of -3.356, a correlation coefficient of 0.998, and an amplification efficiency of 98.589%. Experiments were carried out on the rice flour mixed with 50%, 10%, 1%, 0.1%, 0.01%, and 0.001% of wheat. The result showed that it was possible to detect samples mixed with up to 0.01% of wheat. As a result of checking, the wheat detection potential of rice, 34 processed foods, and seven processed foods was ascertained. The real-time PCR method using the wheatspecific primer and probe developed in this study can be used to identify the authenticity of the raw materials, such as the incorrect indication of the raw materials utilized and the unintended mixing of wheat during the manufacturing process.

오메가-3 제품의 안전성을 알아보기 위하여, 경기지역에 유통되는 20개의 fish oil과 algae oil을 원료로한 건강기능 식품 오메가-3에 대하여 EPA와 DHA의 함량과 산화 정도를 조사하였다. 산가의 결과값은 0-2.9 mg/g으로 평균 및 표준편차는 0.5 ± 0.6이며 CODEX/FAO의 기준 3.0 mg/g을 적용하였을 때 모두 적합하였으며, 과산화물가의 경우 2.6-14.1 meq/kg로 평균 및 표준준편차는 5.5 ± 2.9이며, 기준 5.0 meq/kq을 적용하였을 때 20건 중 11건이 적합하고 9건이 기준을 초과하였다. 아니시딘가는 국제적인 기준을 20을 적용하였을 때 18건이 적합하였으며 2건이 기준을 초과하였다. 총 산화가는 기준 26을 적용하였을 때 16건이 적합하였으며 4건이 기준을 초과하였다. 오메가-3의 산화에 대한 안전성 확보를 위하여 새롭게 설정되어 3월부터 시행되고 있는 산가 및 과산화물가에 대한 기준 올해 11월 시행예정인 아니시딘가와 총산화가에 대한 시행은 매우 바람직하며 지속적인 감시를 통하여 산화로부터의 안전성 확보에 기여할 것으로 보인다.

To evaluate parameters influencing on the dust removal of the High Temperature Filter(HTF) system, a computer simulation of fluid dynamics inside the system had been performed. The results showed that the optimum pulse jet periods were 50ms and 90ms for the 1000mm and 1500mm long filter elements respectively. Dust removal effect was very excellent under the pulse jet pressure of 3 bar. But the distance between the pulse jet nozzle and the venturi of a filter element had no meaningful effect on the performance with the variation from 5mm to 10mm. Compared to the dispersion mode of pulse jet, the collective mode of pulse jet flow was preferable in maintaining the pressure inside the system stable.

파일럿 규모의 유리화플랜트에서 일련의 시험을 통해 고온 세라믹 캔들 필터 시스템의 주요 운전 변수 및 성능을 평가하였다. 실증 시험결과 매 시험초기에는 필터 표면 먼지층(Dust cake)의 생성으로 인해 필터 매질에 걸리는 차압이 급격히 상승하였다. 그런 다음 차압은 곧 일정한 범위에서 안정되었고, 표면유속(Face velocity)에 비례하여 계속적으로 변화하였다. 이와 반대로, 필터 투과율(Permeability)은 매시험 초기에 급격히 감소하였다. 필터표면 먼지의 역세정은 공기압 3～5 bar범위 일때 효율적이었다. 필터 입구 및 출구에서 동시에 등속으로 채취한 먼지농도를 바탕으로 필터의 먼지 포집율(Dust collection efficiency)을 평가한 결과 필터 성능은 설계값인 99.9%과 같은 것으로 나타났다. 100시간의 장기시험을 포함한 일련의 실증시험을 수행하는 동안 고온 필터 시스템의 성능에 영향을 주는 특별한 문제점은 발견되지 않았다.

In order to vitrify the combustible dry active waste (DAW) generated from Korean Nuclear Power Plants, a glass formulation development based on waste composition was performed. A borosilicate glass, DG-2, was formulated to vitrify the DAW in an induction cold crucible melter (CCM). The processability, product performance, and volume reduction effect of the candidate glass were evaluated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product of the glass product such as chemical durability, phase stability, and density was satisfactory. The vitrification process using the candidate glass was also evaluated assuming that it was operated as economically as possible.

원자력발전소에서 발생하는 이온교환수지와 가연성잡고체 혼합폐기물을 유리화하기 위하여 유도 가열식 저온용융로를 이용한 실증시험을 수행하였다. 금속 티타늄 고리(Ti-ring)를 이용한 유리의 초기점화에 필요한 에너지는 약 290 kWh로 평가되었다. 혼합폐기물의 투입 중 고주파발생기의 출력은 160∼190 kW로 임피던스는 0.55∼0.65 범위 내에서 안정적으로 유지되었다. 이온교환수지 단독투입 시 보다 가연성잡고체와 혼합 할 경우 CO 발생농도는 1/40 정도로 낮아졌는데, 이는 1.8배 정도 높은 연소에너지를 갖는 가연성잡고체가 혼합폐기물의 완전연소를 유도한 것으로 평가되었다. 혼합폐기물의 공급량에 적당한 최적 산소 버블링에 의해 유리 용탕 내부로의 미연폐기물의 함침은 발생하지 않았으며 유리 용탕은 지속적으로 공정 건전성을 유지하였다. 유리 용탕의 부피가 증가하는 팽창(swelling) 현상 때와 정상 일 때 발생가스를 측정, 비교한 결과 swelling 현상 때는 NO와 같이 환원성 가스의 농도 보다 산화성 기체인 의 농도가 높은 것으로 나타났다. 실증시험에 사용된 이온교환 수지와 가연성잡고체의 각각 투입량은 368kg과 751kg 이었으며, 74 정도의 감용비를 달성하였다.