Background: Efficient gene editing technology is needed for successful knock-in. Homologous recombination (HR) is a major double-strand break repair pathway that can be utilized for accurately inserting foreign genes into the genome. HR occurs during the S/G2 phase, and the DNA mismatch repair (MMR) pathway is inextricably linked to HR to maintain HR fidelity. This study was conducted to investigate the effect of inhibiting MMR-related genes using CdCl2, an MMR-related gene inhibitor, on HR efficiency in HC11 cells. Methods: The mRNA and protein expression levels of MMR-related genes (Msh2, Msh3, Msh6, Mlh1, Pms2), the HR-related gene Rad51, and the NHEJ-related gene DNA Ligase IV were assessed in HC11 cells treated with 10 μM of CdCl2 for 48 hours. In addition, HC11 cells were transfected with a CRISPR/sgRNA expression vector and a knock-in vector targeting Exon3 of the mouse-beta casein locus, and treated with 10 μM cadmium for 48 hours. The knock-in efficiency was monitored through PCR. Results: The treatment of HC11 cells with a high-dose of CdCl2 decreased the mRNA expression of the HR-related gene Rad51 in HC11 cells. In addition, the inhibition of MMR-related genes through CdCl2 treatment did not lead to an increase in knock-in efficiency. Conclusions: The inhibition of MMR-related gene expression through high-dose CdCl2 treatment reduces the expression of the HR-related gene Rad51, which is active during recombination. Therefore, it was determined that CdCl2 is an inappropriate compound for improving HR efficiency.

목적 : 본 연구에서는 다양한 방법의 시각적 수행을 실시하는 시기능 훈련에 있어서 원, 근거리 외사위를 가진 남녀의 시기능훈련 전, 후 성별 차이에 따른 주시시차에 미치는 영향에 대하여 알아보고자 하였다. 방법 : 대상자는 20대의 성인 남녀 총 30 명으로 교정시력은 양안 1.0 이상이며 사시자는 실험에서 제외되었 다. 시기능훈련 전, 후 양안시기능 검사와 주시시차 검사를 실시하였고 그 중 외사위를 가진 대상자의 시기능훈련 전, 후 외사위량 감소와 주시시차의 향상도를 남녀 성별에 따라 비교 분석하였다. 결과 : 원거리 시기능훈련 전, 후 남녀(남자: 11명, 여자: 16명)에 따른 외사위 감소량은 남자일 때 시기능훈련 후 외사위량이 1.50±0.79Δ으로 유의하게 감소하였고(p=0.046), 여자일 때 시기능훈련 후 외사위량이 1.56±0.50Δ 으로 유의하게 감소하였다(p=0.005). 반면, 주시시차에서 남자는 6.70±2.29로 유의한 감소를 보였으나(p=0.042), 여자의 경우 3.49±0.89로 유의한 감소는 없었다(p=0.655). 근거리 시기능훈련 전, 후 남녀(남자: 14명, 여자: 14명) 에 따른 외사위 감소량은 남자일 때 시기능훈련 후 외사위량이 5.50±1.56Δ으로 유의하게 감소하였고(p=0.036), 여자일 때 시기능훈련 후 외사위량이 4.28±0.88Δ으로 유의하게 감소하였다(p=0.004). 반면, 주시시차 검사에서 남자는 4.96±1.03으로 유의한 감소를 보였으나(p=0.031), 여자의 경우 3.37±0.92로 유의한 감소는 없었다 (p=0.655). 결론 : 남녀 성별에 따른 외사위의 주시시차는 시기능 훈련 후 여성보다 남성에서 주시시차가 감소되었음을 유 의미하게 확인할 수 있었다.

본 연구는 민간기업과는 다른 특성을 보이는 공공기관 HRD의 평가지표 도출이 필요하다는 문제의식에 서 출발하였으며, 공공기관 HRD 체계의 타당한 평가 준거 개발을 목적으로 한다. 이를 위해 CIPP 모형을 활용하여 공공부문 HRD체계와 과정 준거를 개발했던 연구사례를 분석하고, 국내 공공기관 인적자원개발 실무자 6인 대상의 심층 인터뷰를 실시하여 15개 평가영역, 41개 평가항목, 56개 평가지표로 구성된 평가 준거 초안을 도출하였다. 평가준거 초안에 대한 타당성을 확보하고자 학계, 실무, 컨설팅 전문가 12인을 대상으로 2차의 델파이 조사를 거쳐 평가 준거를 확정하였다. 최종적인 평가 준거는 요구분석, 기관장 리더 십, HRD 인력 전문성, 경영성과 등 15개 영역, 37개 항목, 45개 지표로 도출되었다. 본 연구는 공공기관의 양면적 성격을 반영한 공공기관 HRD 체계의 평가 준거를 제시했다는 데 의의가 있다. 본 연구는 다양한 공공기관의 사업 특성을 감안한 평가 준거 보완이 필요하다는 점을 제언하였다.

Cs-137, a radioactive isotope of caesium, is a commonly occurring fission product that is generated during the nuclear fission of U-235 and other fissionable isotopes in both nuclear reactors and weapons. Due to its long half-life of about 30 years and propensity to accumulate in sediments and marine organisms, Cs-137 is considered a major radionuclide for environmental radioactivity monitoring. In April 2021, as the Japanese government decided to discharge Fukushima contaminated water into the sea, the monitoring of marine radioactivity in South Korea has become increasingly significant. In this study, as an initial step towards establishing a standardized procedure for analyzing radioactive caesium in seawater, the radioactivity of Cs-137 was analyzed on a 2 L of seawater spiked with 10 Bq of Cs-137 standard solution supplied by KRISS. The seawater was collected from Im-nang Beach, situated at a distance of approximately 2 kilometers from DIRAMS. The radioactivity of Cs-137 in seawater was determined according to the improved AMP procedure presented by M.Aoyama in 2000. The seawater was pretreated using Ammonium Phosphomolybdate (AMP) coprecipitation, which has a high selectivity for caesium (Kd = ~5500), and the activity of Cs-137 was determined by gammaspectroscopy and subsequently corrected via the weight yield. The weight yield of the dried AMP/Cs compound was more than 93%. For the gamma-spectroscopy analysis, the AMP/Cs compound was dissolved in a cylindrical U8 beaker with NaOH to ensure that its shape and volume were consistent with the CRM (KRISS, 221U890-1) used to calibrate the detector. The dissolved compound was then positioned directly onto the detector housing and subjected to a measurement duration of 80,000 seconds utilizing a p-type HPGe (Ortec, GEM60) with a relative efficiency of 54%. The activity of Cs-137 was determined to be 10.81 Bq, confirming the reproducibility of the AMP coprecipitation and weight yield methods. The present experiment was carried out using a 2 L sample, but a large volume of seawater would be required to achieve a sufficient minimum detectable activity (MDA) for Cs-137 in natural seawater. Thus, a standardized procedure for analysis of radioactive caesium in natural seawater will be established through the analysis of a large volume of seawater in future studies.

In this study, in relation to the demolition of the building as a research reactor, in order to establish a basic design for preparation for relocation and installation of the TRIGA Mark-II, the present conditions such as actual measurements and structural safety were investigated, as well as technologies and cases related to the relocation and installation of cultural properties. Based on this, the basic design for the relocation and installation of cultural assets was established by reviewing the disassembly and transport design of the TRIGA Mark-II and the basic plan for the relocation site. Although the structural safety of the current self-weight of the structure is judged to be reasonable, when lifting the structure, it is necessary to consider a method of lifting the foundation by reinforcing the foundation so that the tensile force can be minimized in the structure. As for the technology to be applied before TRIGA Mark-II, the technology before non-transplacement was confirmed as the most reasonable method in terms of preserving the original form, securing safety, and securing economic feasibility. Among the non-replacement technologies, the methods that can be applied before reactor 1 can be largely classified into three types. The three methods to be reviewed can be largely classified into the traditional rail movement method, the movement method using transport equipment, and the crane movement method. Each required period was calculated from the basic design results, and the modular trailer method was judged to be the most efficient. From the basic design results, the required period for each stage according to the mobile construction method was calculated. Depending on the calculation result, the modular trailer method is judged to be the most efficient. However, the final construction method should be selected according to the detailed design results. Overall, the results obtained through this study suggest that it is possible to create a memorial hall without the previous installation of TRIGA Mark-II if the structure foundation is composed independently of the building foundation after conducting a detailed characteristic investigation on the foundation of the TRIGA Mark-II structure.

A person who performs or plans to conduct a physical protection inspection as stipulated by the law, the act on physical protection and radiological emergency, should obtain an inspector’s ID card certified and authorized by Nuclear Safety and Security Commission Order No.137 (referred to as Order 137). In addition, according to Order 137, KINAC has been operating some training courses for those with the inspector’s ID card or intending to acquire it. Also, strenuous efforts have been put to incrementally elevate their inspection related expertise. Since Republic of Korea has to import uranium enriched less than 20% in order to manufacture fuels of nuclear reactors in domestic and abroad, the physical protection for categorization III nuclear material in transit is significantly important along with an increase in transport. The expertise of inspectors should be constantly needed to strengthen as the increase in transport leads to an increase in inspection of nuclear material in transit. We have suggested a special way to improve the inspector’s capacities through Virtual Reality technology (VR). A 3-Dimensional virtual space was designed and developed using a 3-axis simulator and VR equipment for practical training. HP’s Reverb G2 product, which was developed in collaboration with VALVE Corporation and MicroSoft, was used as VR equipment, and the 3-axis motion simulator was developed by M-line STUDIO corp. in Korea for the purpose of realizing virtual reality. The training scenarios of transport inspection consist of three parts: preparation at the shipping point, transport in route including stops and handover at the receiving point. At the departure point, scenario of the transport preparation is composed with the contents of checking the transport-related documents which should be carried by shipper and/or carrier during transport and confirming who the shipper and/or carrier is. Second, scenario is designed for inspector to experience how carrier and/or shipper protect the nuclear material during transport or stops for rests or contingency and how they communicate with each other during transport. Lastly, scenario is developed focusing on key check items during handover of responsibilities to the facility operator at the destination. Those training scenarios can be adopted to strengthen the capabilities of those with inspector’s ID card of physical protection in accordance with Order 137 and to help new inspectors acquire inspectionrelated expertise. In addition, they can be used for domestic education to promote understanding of nuclear security, or may be used for education for people overseas for the purpose of export of nuclear facilities.