Background: A functional movement screen (FMS) can be used as an intervention method as well as a test method. Compensatory action due to a faulty functional movement result in imbalance of the body, and decrease in proprioceptive sensation and flexibility. However, the benefits of exercise using FMS on proprioceptive sensation and flexibility are unclear. Objectives: This study aimed to investigate the effect of exercise using FMS on the proprioceptive sensation and flexibility. Design: Pretest-posttest control group experimental design. Methods: Fifty-two young adults in their 20s were divided into an FMS exercise group (FEG, n=26) and a control group (CG, n=26). The FEG conducted FMS exercise intervention for 12 days, and CG did not implement any intervention. Each group evaluated proprioceptive sensation and flexibility before and after exercise. To measure proprioceptive sensation, the angles were measured at both shoulder joints, elbow joints, hip joints, and knee joints using the active joint sensory position test method. To measure flexibility, situp forward bending evaluation was performed. Results: In the FEG, bilateral proprioceptive sensation and flexibility improved significantly after intervention (all P<.01). There were no significant differences in the CG (all P>.05). After the intervention, there were significant differences between the groups in both proprioceptive sensation and flexibility (all P<.05). Conclusion: The findings suggest that exercise using FMS can significantly improve proprioceptive sensation and flexibility. Therefore, it is suggested to consider exercise using FMS as an intervention to increase joint proprioceptive sensation and flexibility.

Repetitive or excessive exposure to ultraviolet (UV) radiation causes oxidative stress-mediated skin photoaging through the overproduction of reactive oxygen species. Actinidia polygama is known as a medical plant used in oriental medicine for treating several diseases such as abdominal pain, stroke and rheumatoid arthritis. Recently, it was reported that A. polygama extract had anti-wrinkle and skin hydrating properties in ultraviolet B (UVB)-exposed hairless mice. However, the molecular biological mechanism of this extract on alleviating skin photoaging is still unknown. Therefore, we investigated the anti-photoaging effects of PB203, which is the powder of A. polygama extract, in the in vivo and in vitro photoaging models. First, PB203 showed 2,2’-azino-bis(3-ethylbenzothiazoline-6-sulfonic acid) and 2,2-diphenyl-1-picrylhydrazyl radical scavenging activities due to the presence of anti-oxidant components including flavonoids and polyphenols. In UVB-irradiated hairless mice, oral administration of PB203 (100 mg/ kg) significantly improved wrinkle formation, skin dehydration, elasticity and skin barrier function by decreasing the levels of matrix metalloproteinases (MMPs) and increasing those of collagen I, filaggrin, involucrin and loricrin. Especially, the reduced production of p-p38, p-c-Jun and p-c-Fos by PB203 reversed the elevated levels of MMPs mediated by UVB exposure, resulting in the upregulation of collagen I expression. Consistent with these animal data, PB203 remarkably enhanced the mRNA expression of collagen I, filaggrin, involucrin and loricrin, while suppressed that of MMPs in UVB-irradiated HaCaT cells. And PB203 increased the wound recovery rate of cells by promoting their proliferation and migration. Moreover, PB203 significantly recovered the activity of superoxide dismutase inhibited by UVB in both mice and cells. In conclusion, PB203, which protects skin from UVB-induced photodamage by exerting antioxidant properties, can be considered to have sufficient potential as a functional ingredient or therapeutic agent improving skin photoaging and related skin symptoms.

Complexing agents used at various nuclear facilities exist in low- and intermediate level radioactive wastes deposited in the repository site. In addition these will be generated through the degradation of the wastes such as cellulose materials. The presence of chelating agents may possibly affect the safety of the wastes repository by promoting the migration of radionuclides into geosphere. Thus, under Nuclear Safety and Security Commission’s Notice No. 2021-16, the contents of chelating agents in radioactive wastes are required to be determined for the secured disposal. UV-Vis method based on an enzymatic reaction was proved to be in adequate to analyze citric acid in radioactive wastes with complex matrix, especially for concrete. A rapid automated method using ion chromatography (IC) for analysis of citric aicd in concrete samples is developed. This automated method enables a sample solution to measure without pretreatment and a target substance to separate from other concrete admixtures. Also, the developed method here, for radioactive concrete wastes was successfully applied to real samples with lowering a limit of quantification value.

This study introduces the licensing process carried out by the regulatory body for construction and operation of the 2nd phase low level radioactive waste disposal facility in Gyeongju. Also, this study presents the experience and lessons learned from this regulatory review for preparing the license review for the next 3rd phase landfill disposal facility. Korea Radioactive Waste Agency (KORAD) submitted a license application to Nuclear Safety and Security commission (NSSC) on December 24, 2015 to obtain permit for construction and operation of the national engineered shallow land disposal facility at Wolsong, Gyeongju. NSSC and Korea Institute of Nuclear Safety (KINS) started the regulatory review process with an initial docket review of the KORAD application including Safety Analysis Report, Radiological Environmental Report and Safety Administration Rules. After reflecting the results of the docket review, the safety review of revised 10 application documents began on November 29, 2016. Total 856 queries and requests for additional information were elicited by thorough technical review until November 16, 2021. As the Gyeongju and Pohang earthquakes occurred in September 2016 and November 2017, respectively, the seismic design of the disposal facility for vault and underground gallery was enhanced from 0.2 g to 0.3 g and the site safety evaluation including groundwater characteristics was re-investigated due to earthquake-induced fault. Also, post-closure safety assessments related to normal/abnormal/human intrusion scenarios were re-performed for reflecting the results of site and design characteristics. Finally, NSSC decided to grant a license of the 2nd phase low level radioactive waste disposal facility under the Nuclear Safety Laws in July 2022. This study introduces important issues and major improvements in terms of safety during the review process and presents the lessons learned from the experience of regulatory review process.

High Integrity Container (HIC) made of polymer concrete was developed for the efficient treatment and safe disposal of radioactive spent resin and concentrate waste in consideration of the disposal requirements of domestic disposal sites. Permission for application of Polymer Concrete High Integrity Container (PC-HIC) to the domestic nuclear power plants (NPPs) has been completed or is under examination by the regulatory agency. In the case of 860 L PC-HIC for very-low-level-waste (VLLW) or low low-level-waste (LLW), the application of four representative NPPs has been approved, and the license for extended application to the rest NPPs is also almost completed. A licensing review is also underway to apply 510 L PC-HIC for intermediate and low-level-waste (ILLW) to representative nuclear power plants. In order to handle and efficiently store and manage PC-HICs and high-dose PCHIC packages, a gripper device that can be remotely operated and has excellent safety is essential, and the introduction of NPPs is urgent. The conventional gripper device developed by the PC-HIC manufacturer for lifting test to evaluate the structural integrity of PC-HIC requires a rather wide storage interval due to its design features, and does not have a passive safety design to handle heavy materials safely. In addition, work convenience needs to be reinforced for safety management of high radiation work. Therefore, we developed a conceptual design for a gripper device with a new concept to minimize the work space by reflecting on-site opinions on the handling and storage management conditions of radioactive waste in NPPs, and to enhances work safety with the passive safety design by the weight of the package and the function of checking the normal seating of the device and the normal operation of the grip by the detector/indicator, and to greatly improves the work efficiency and convenience with the wireless power supply function by rechargeable battery and the remote control function by camera and wireless monitoring & control system. Through design review by experts in mechanical system, power supply and instrumentation & control fields and further investigations on the usage conditions of PC-HICs, it is planned to facilitate preparations for the application of PC-HIC to domestic NPPs by securing the technical basis for a gripper device that can be used safely and efficiently and seeking ways to introduce it in a timely manner.