코로나 사태 이후 공연예술계는 ‘초지능화’와 ‘초연결성’의 특징으로 대표되는 메타버스에 주목 하기 시작했다. 직접 만나서 소통할 수 없는 비대면적 상황은 현실세계와 가상공간을 연결해 주는 메타버스 플랫폼 전시 공연 활성화에 큰 영향을 끼쳤다. 코로나 사태가 끝난 이후에도 공연예술계는 다양하고 실험적인 온-오프라인 공연의 형태로 해당 기술을 활용한 다양한 프로 젝트 전시들을 선보이고 있다. 이처럼 실감 콘텐츠와 가상현실을 접목한 VR, XR 기술들은 빠 르게 실감 콘텐츠와 전시공연분야에 접목되며 실험적이고 다양한 공연과 전시를 선보이고 있 다. 메타버스 플랫폼을 활용한 전시와 공연들이 관객들이 어떠한 방식으로 다가가고 있는지 실감 콘텐츠 공연사례들을 분석하고, 가상현실이 일상화되고 있는 요즘, 전시와 공연 예술 분 야의 변화의 방향을 살펴본다.

The occurrence of shear failure in a rock mass, resulting from the sliding of joint surfaces, is primarily influenced by the surface roughness and contact area of these joints. Furthermore, since joints serve as crucial conduits for the movement of water, oil, gas, and thermal energy, the aperture and geometric complexity of these joints have a significant impact on the hydraulic properties of the rock mass. This renders them critical factors in related industries. Therefore, to gain insights into the mechanical and hydraulic behavior of a rock mass, it is essential to identify the key morphological characteristics of the joints mentioned above. In this study, we quantified the morphological characteristics of tensile fractures in granitic rocks using X-ray CT imaging. To accomplish this, we prepared a cylindrical sample of Hwang-Deung granite and conducted splitting tests to artificially create tensile fractures that closely resemble rough joint surfaces. Subsequently, we obtained 2D sliced X-ray CT images of the fractured sample with a pixel resolution of approximately 0.06 mm. By analyzing the differences in CT numbers of the rock components (e.g., fractures, voids, and rock matrix), we isolated and reconstructed the geometric information of the tensile fracture in three dimensions. Finally, we derived morphological characteristics, including surface roughness, contact area, aperture, and fracture volume, from the reconstructed fracture.

Rock discontinuities in underground rock behave as weak planes and affect the safety of underground structures, such as high-level radioactive waste disposal and underground research facilities. In particular, rock discontinuities can be a main flow path of groundwater and induce large deformation caused by stress disturbance or earthquakes. Therefore, it is essential to investigate the characteristics of rock discontinuities considering in-situ conditions when constructing highlevel radioactive waste disposal, which needs to assure the long-term safety of the structure. We prepared Hwang-Deung granite rock block specimens, including a saw-cut rock surface, to perform multi-stage direct shear tests as a preliminary study. In the multi-stage direct shear tests, we can exclude possible errors induced by different specimens for obtaining a full failure envelope by using an identical specimen. We applied the initial normal stress of 3 MPa on the specimen and increased the normal stress to 5 and 10 MPa step by step after peak shear stress observation. We obtained the mechanical properties of saw-cut rock surfaces from the experiments, including friction coefficient and cohesion. Additionally, we investigated the effect of filling material between rock discontinuities, assuming the erosion and piping phenomenon in the buffer material of the engineering barrier system. When the filling material existed in the rock surfaces, the shear characteristics deteriorated, and the effect of bentonite was dominant on the shear behavior.

A lot of CANDU Spent Fuels (CSFs) have been stored in spent nuclear fuel pools and dry storage facilities. In accordance with the enhanced nuclear regulations, the initial characteristics of CSF should be inspected to ensure the integrity of CSF and the reliable operation of storage system before loading it into a cask for long-term dry storage. For the inspections, an initial characteristics measurement equipment was designed, which is used for Pool-Side Examination (PSE) in the spent fuel pool of the pressurized heavy water reactor nuclear power plant. Measurements using the equipment consist of non-contact inspections and contact inspections. The non-contact inspections do not affect CSF integrity, whereas the integrity of CSF can be reduced during the contact inspections under abnormal operating conditions because the probe of equipment may apply specific loads to the CSF. Therefore, the structural integrity evaluations of equipment and CSF are performed using Finite Element (FE) analyses for four combinations based on two abnormal conditions and two probe positions. The used abnormal conditions are the pressing load condition and the scratching load condition, and two probe positions are the center and bottom of the fuel rod in the longitudinal direction, respectively. In this evaluation, the bottoms of the fuel rod or CSF are defined as the regions facing the bottom surface of equipment. The analysis of the pressing load condition is performed by pressing the probe of the equipment in radial direction of the CSF fuel rod. That of the scratching load condition is carried out by applying a specific radial load to the CSF fuel rod using the probe and then applying the load to the surface of the fuel rod while moving axially along the surface. All combinations are analyzed considering geometric, boundary and material non-linearity under the dynamic load, which is dependent on the equipment operating velocity. The stresses of CSF and equipment components were obtained from these analyses. The maximum stress of each component was generated at the combination on the scratching load condition for the bottom position among the four combinations. The obtained maximum stresses are lower than the yield stress for each component material. Also, the CSF is not overturned due to the support plate of the equipment in all analyses. Therefore, the structural integrity and safety of the equipment and the CSF are maintained under abnormal operating conditions during the inspection using the initial characteristic measurement equipment.

For safe management of spent nuclear fuels, they should be delivered to repository or waste disposal site. As the amount of spent nuclear fuel transportation is expected to increase in the future due to the provision of an intermediate storage facility, the necessity to secure transportation cask is emerging. In order to secure the spent nuclear fuel transportation cask, it is necessary to analyze the regulatory processes for domestic and foreign spent nuclear fuel transportation cask. In this study, the regulatory processes for domestic and foreign spent nuclear fuel transportation cask was analyzed. In this study, the IAEA, US, and Korea spent nuclear fuel transportation cask regulatory processes were analyzed. The domestic and foreign spent nuclear fuel transportation cask regulatory processes consist of design phase, manufacturing phase, and operation phase. In the design stage, the transport requirements are designed in accordance with the safety requirements of international organizations and countries. The application to be submitted when applying for approval should include a safety analysis report, evidence proving compliance with safety requirements et al. In the manufacturing stage, it is a stage to check whether the safety requirements are satisfied before the first use after manufacturing the transportation cask. Inspections include welding inspection, leakage inspection, shielding inspection, and thermal inspection. In the operation stage, it is a stage of periodically performing inspections for continuous maintenance of the package when the transportation cask is used. The inspection items to be performed are similar to the manufacturing stage and typically include performance inspection of components and leakage inspection. In this study, domestic and foreign spent nuclear fuel transportation cask regulatory processes were analyzed. It was found that the domestic and foreign spent nuclear fuel transportation cask regulatory processes consist of the design phase, the manufacturing phase, and the operation phase. The results of this study can be used as basic data for policy decision-making for the spent nuclear fuel cask.

게임을 구현하는 동안 주기성을 보장해야될 필요성이 있는 경우가 많이 있다. 예를 들어 많은 경우에 캐릭 터의 충돌은 주기적으로 처리되어야 될 필요성이 있는데 주기적으로 처리하지 못하는 경우 게임에서 충돌 을 감지하지 못하는 경우가 발생할 수 있다. 또한 슈팅 게임에서는 많은 경우에 사용자의 편의를 위하여 특 정 버튼을 누르면 무기를 자동적으로 발사하는 기능을 포함하고 있어 주기적으로 무기를 발사해야될 필요 성이 있다. 한편 유니티를 사용하여 게임을 구현할 때 이러한 주기성을 보장하기 위해서 WaitForSeconds로 지연을 발생시킨 코루틴, InvokeRepeating, FixedUpdate, .NET의 Timers.Timer가 사용될 수 있다. 그러나 이러한 다양한 방법들로 인하여 방법의 선택에 어려움이 있어 연구를 진행하였다. 본 연구에서는 1분 동안 6000번 메서드를 주기적으로 실행하고 주기성과 횟수를 측정하였다. 또한 다양한 환경에서의 실험을 위하여 추가의 모델 렌더링이 없는 경우와 렌더링을 추가한 경우, 다양한 해상도에서 주기성과 메서드 호출 횟수를 모두 측정했다. 실험 결과, 부하가 적은 환경에서는 InvokeRepeating이 가장 6000회에 가까웠으며 부하가 큰 환경 에서는 Timers.Timer가 가장 6000회에 가까웠으며 실행 주기의 편차가 가장 적었다. 이러한 실험들을 통하여 유니티를 통하여 게임을 구현할 때 일정 시간 내에 실행되는 횟수가 중요한 게임에서 성능 부하가 크지 않 은 경우 InvokeRepeating을, 성능 부하가 크다면 .NET의 Timer를 쓰는 것이 적합함을 알아내었다. 본 연구를 통하여 개발자는 유니티에서 제공되는 주기성 제공 방법들 중에서 적절한 방법을 선택할 수 있다.

독립형 VR기기가 활발히 개발되기 전 스마트폰을 HMD로 만들려는 움직임이 있었고 구글의 카드보드와 삼 성의 기어 VR이 그 예이다. 하지만 독립형 VR기기의 출시와 모바일 기기의 한계로 현재는 대부분 AR로 전 환되어 사용되었다. 그렇지만 지난 10년간 모바일 VR과 AR의 기술도 발달했지만, 그동안 모바일 기기의 성 능도 향상되었다. 따라서 발달한 기술들을 바탕으로 손 추적을 뛰어넘어 손동작 분류를 모바일 기기에서 기 존의 VR과 AR 콘텐츠와의 상호작용에 활용할 수 있다. 본 논문에서는 Manomotion을 이용하여 2D 또는 3D 의 골격을 추적하고 손동작 분류를 구현했으며 게임을 사용하여 검증하였다.

In Korea, research on the introduction of dry storage facility is being conducted as an alternative to saturation of temporary storage facilities for spent nuclear fuel. The introduction of dry storage facilities requires a radiological impact assessment on the workers of the facility, and for this, an appropriate exposure scenario must be derived through work procedure analysis. In this study, the procedure for storing spent nuclear fuel in dry storage facilities was analyzed based on the case of evaluating the radiological impact of workers in dry storage facilities abroad. We investigated cases of radiological impact assessment on workers at on-site dry storage facilities by PNNL, Dominion, and P. F. Weck. PNNL and Dominion analyzed the storage work procedure of the VSC (Vertical Storage Cask) method using CASTOR V/21, TN-32, respectively, and conducted a radiological impact assessment. P. F. Weck analyzed the storage work procedure of various spent nuclear fuel casks for VSC and HSM (Horizontal Storage Module), conducted a radiological impact assessment. As a result of comparing the procedure for storing spent nuclear fuel by case, it was found that the storage procedure was determined by the storage method and the cask type. In the case of VSC method, canister-type casks and basket-type casks are used, and the storage procedure are partially different according to each. Canister-type cask requires repackaging from transfer overpack to storage overpack, but basket-type cask doesn’t require that procedure. In the case of the HSM method, only the canister type cask was found to be used. However, the storage procedure was different depending on the type of HSM system. Depending on the type of HSM system, the necessity of cask for on-site transport was different. In this study, we investigated and analyzed the work procedure according to the storage method of dry storage facilities abroad. It was found that the dry storage procedure of spent nuclear fuel different according to the storage method and type of cask. The results of this study can be used as basic when deriving the exposure scenario for spent nuclear fuel dry storage workers suitable for the domestic situation.

Non-destructive estimation of leaf area is a more efficient and convenient method than leaf excision. Thus, several models predicting leaf area have been developed for various horticultural crops. However, there are limited studies on estimating the leaf area of strawberry plants. In this study, we predicted the leaf areas via nonlinear regression analysis using the leaf lengths and widths of three-compound leaves in five domestic strawberry cultivars (‘Arihyang’, ‘Jukhyang’, ‘Keumsil’, ‘Maehyang’, and ‘Seollhyang’). The coefficient of determination (R2) between the actual and estimated leaf areas varied from 0.923 to 0.973. The R2 value varied for each cultivar; thus, leaf area estimation models must be developed for each cultivar. The leaf areas of the three cultivars ‘Jukhyang’, ‘Seolhyang’, and ‘Maehyang’ could be non-destructively predicted using the model developed in this study, as they had R2 values over 0.96. The cultivars ‘Arihyang’ and ‘Geumsil’ had slightly low R2 values, 0.938 and 0.923, respectively. The leaf area estimation model for each cultivar was coded in Python and is provided in this manuscript. The estimation models developed in this study could be used extensively in other strawberry-related studies.