본 연구는 배수지에서 저수조를 포함한 대수용가의 수도꼭지에 이르는 구간에서 탁도와 잔류염소 농도의 시간적⋅공간적 변화를 분석하였다. 모니터링은 배수지, 중블록 유입 지점, 대수용가 유입 지점, 저수조 유출 지점, 수도꼭지 등 5개 지점에서 수행되었으며, 유량, 잔류염소, 탁도, pH, 전기전도도, 온도를 측정하였다. 연구 결과, 수돗물 이동 경로를 따라 잔류염소 농도는 점차 감소하고 탁도는 증가하는 경향을 보였다. 특히, 비업무시간대에는 수돗물 정체로 인한 수질 저하가 확인되었다. 또한, 저수조의 건전성을 평가하기 위해 반응계수를 산출한 결과, 시간에 따른 저수조 내부 건전성 저하와 수질 악화 가능성이 확인되었다. 본 연구는 수돗물의 이동 거리, 사용 시간대, 유량 변화 및 공급 방식에 따라 수질이 달라질 수 있음을 보여주며, 저수조에 의존하는 지역에서는 안전한 수돗물 공급을 위해 지속적인 모니터링과 관리가 필요함을 시사한다.

The rapid urbanization and industrial growth have increased the demand in construction, maintenance, and infrastructure, leading to significant advancements in aerial work vehicle technology. This study focuses on the structural performance of ultra-high-strength steel plates of varying thicknesses used in telescopic booms, which is a critical component of aerial work vehicles. This study aims to address the cost issues associated with the previously used 5mm thick plates by evaluating the structural integrity of thinner plates. Using finite element analysis (FEA), the study analyzes stress and displacement for different thicknesses, specifically targeting the first boom segment, which bears the most load. The results indicate that while 3mm and 3.2mm thick plates are unsuitable due to buckling, the 4mm thick plate meets safety criteria with a safety factor of 2.51 and reduces costs by over 20%. By using 4mm thick ultra-high-strength steel for the first boom segment is cost-effective, providing structural integrity and an applicable solution for aerial work vehicle manufacturers.

In this study, we examined number, motility and plasma membrane integrity of spermatozoa from six regions of epididymis in bull. Six testicles with epididymides were castrated from six bulls (mean±standard error, age of days = 441.3±9.6, body weight (kg) = 367±8.4, scrotal circumference (cm) = 30.7±0.4) at Hanwoo Research Institute, NIAS and transported to laboratory within 1 hour. Testicular weight, length, width and circumference were recorded. Epididymis in each bull was randomly used for recovery of spermatozoa. Epididymis was divided into six regions: efferent duct (ED), caput, corpus, proximal cauda (Pcauda), distal cauda (Dcauda) and vas deferens (VD). In experiment 1, we examined sperm number of each region of epididymis. Each region of epididymis contained different number of spermatozoa: ED (37.8±15.7 × 106cells/ml, 8.2%), caput (93.6±18.8 × 106cells/ml, 20.2%), corpus (33.0±8.5 × 106cells/ml, 7.1%), Pcauda (104.2±23.5 × 106cells/ml, 22.5%), Dcauda (180.5±32.5 × 106cells/ml, 39.0%) and VD (14.0±5.0 × 106cells/ml, 3.0%). In experiment 2, sperm motility of each epididymal region was examined by computer assisted sperm analysis (SCA, MicroOptic) system. Sperm motility was divided into 4 groups (fast progressive, slow progressive, non-progressive and immotile) based on WHO guideline. Percentages of fast progressive of Pcauda and Dcauda (11.0±2.3 and 15.4±3.6%) were significantly higher than that of ED, Caput, Corpus and VD which is 0.1±0.1, 1.5±0.6, 1.9±0.7 and 0.3±0.2%, respectively (p<0.05). In experiment 3, percentage of intact plasma membrane spermatozoa of each regions were examined by hypoosmotic swelling test. Percentages of intact plasma spermatozoa were not significantly different among six regions of epididymis: ED, caput, corpus, Pcauda, Dcauda and VD which is 68.0±8.6, 74.0±5.3, 68.5±6.2, 70.8±5.5, 71.0±5.8 and 64.6±10.8%, respectively. In conclusion, in the present study, we found out distribution, motility and plasma membrane integrity of spermatozoa from six regions of epididymis in Hanwoo bull. These results will be contributed to basic research about spermatozoa transportation and characters in epididymis of bull.

In this study, we examined total number, motility and plasma membrane integrity of epididymal spermatozoa from cauda epididymis of bull after preservation at 4ºC. Totally, 23 testicles were castrated from 23 bulls (mean±standard error, age of days = 426.0±7.3, body weight (kg) = 379.7±8.4, scrotal circumference (cm) = 31.0±0.4) at Hanwoo Research Institute, NIAS, and transported to laboratory and preserved on 1, 4 and 6 days at 4 ºC. As control, epididymal spermatozoa recovery from 7 testicles was conducted after transportation to laboratory immediately. In experiment 1, we compared total number of spermatozoa among groups. Total number of spermatozoa from epididymis was not significantly on different preservation day of 0, 1, 4 and 6 which is 1778.0±304.7, 1824.8±343.9, 1228.4±91.7, 1201.8±178.6×106 cells/ml, respectively). In experiment 2, we examined spermatozoa motility and motility parameters (VCL (μm/s), VSL (μm/s), VAP (μm/s), LIN (%)) by computer assisted sperm analysis (SCA, MicroOptic) system. Percentage of motile on 0 and 1 day (88.9±5.2 and 85.8±6.1) was significantly higher than that on 4 and 6 days (32.6±6.5 and 34.3±8.25). Percentage of VCL (μm/s) on 0 and 1 day (93.5±7.6 and 83.0±14.9) was significantly higher than that on 4 and 6 days (36.6±5.1 and 39.5±5.5) (p<0.05). Percentage of VSL (μm/s) on 0 day (28.0±2.1) was significantly higher than that on 1, 4 and 6 days (20.2±3.0, 9.0±2.0 and 8.5±1.6, p<0.05). Percentage of VAP (μm/s) on 0 and 1 days (49.4±3.8 and 41.3±6.6) was significantly higher than that on 4 and 6 days (18.2±3.0 and 19.3±2.8, p<0.05). Percentage of LIN (%) on 0 day (30.7±2.6) was significantly higher than that on 4 and 6 days (23.4±2.7 and 21.1±1.0, p<0.05). Motility of spermatozoa was divided into 4 groups (fast progresive, slow progressive, non-progressive and immotile) based on WHO guideline. Percentage of fast progressive on day at 0 was significantly higher than that on 1, 4 and 6 days (0, 1, 4 and 6 days vs. 19.8±1.9, 10.2±1.1, 2.6±1.0 and 2.3±1.2%, respectively). In conclusion, cauda epididymal spermatozoa should be recovered within one day after preservation at 4 ºC to recover high quality of epididymal spermatozoa in Hanwoo bull

본 연구는 수중 및 여가활동에 대한 수요 증가에 따른 다이버들을 위한 보트의 구조 건전성에 관한 것이다. 대상 선박은 선체 중앙부에 Moon Pool 구조를 갖추고 있는 소형 쌍동선이며, 연구수행은 ISO Rule 기반의 허용응력 산정을 통한 유한요소 해석법을 이용하여 연구를 수행하였다. 연구수행 방법은 ISO 12215-5와 TC118.1225-7에서 정의하고 있는 계수를 산정하고, 종방향굽힘 모멘트, 비틀림 모멘트, 선저슬래밍 하중 등을 적용하여 ISO 기준과 허용응력 설계법(ASD)에 의한 적합성 여부를 판정하고 유한요소해석(FEA)를 활용한 극한강도 설계법을(LFRD)를 적용하여 수행하였다. 연구결과 문풀형 구조를 가진 선박도 ISO규정, KR규정을 적용하여 설계시 구조적 건전성을 확보 하는 것으로 사료된다.

This paper relates to the study of load characteristics applicable to wind turbine generators induced by earthquakes. An artificial design earthquake wave generated through the target spectrum and the envelope function of Richter Magnitude Scale (ML) 7.0 as in ASCE4-98 was created. A simulation of earthquake loads were performed according to the design load cases (DLC) 9.5~9.7 of GL guidelines. Additionally, simulation of seismic loads experienced by Wind Turbines installed in the Gyeongju region were carried out utilizing artificial earthquakes of ML 5.8 simulating the real earthquakes during the Gyeongju Earthquakes of Sept. 2016.

내염소성 원생동물인 크립토스포리디움, 지아디아 등 병원성 미생물의 제거에 대한 신뢰성을 확보하기 위해 정수 처리 공정에서 막여과 시스템이 각광받고 있으며, 이러한 신뢰성을 보증하기 위해 막 완결성에 대한 연구가 중요시되고 있다. 막 완결성 시험은 크게 직접법과 간접법으로 분류되는데, 직접법 중 압력기반의 시험은 버블포인트 이론을 근간으로 병원성 미생물의 최소 크기인 3 μm 크기 이상을 감지할 수 있는 감도로 USEPA Guidance Manual에서 제시하고 있다. 간접법은 온라 인 상태에서 연속적인 운전이 가능하다는 점에서 널리 사용되지만, 직접법에 비해 현저히 낮은 막 손상 감지 감도를 가지고 있 으며, 손상 부위를 특정 지을 수 없는 한계가 있기에 이러한 감지 감도를 개선해야 할 필요가 있다. 따라서 본 연구에서는 압 력 손실 시험에 의한 막 완결성 시험을 통해 막 파단 형태별, 파단 개수, 초기설정압력값에 따른 압력손실률과 LRVDIT 신뢰 성 범위를 상호 비교함으로써 막 손상에 따른 감도의 결과를 정량화하여 UCL 기준을 나타내어 비교 평가하였다.

This study evaluated the mechanical joining characteristics of substrate Al7075 using the filler metals of ER5356 and Al7075 to secure the joining integrity of the specimens by GTAW. The results of radiographic test show that the welded specimens meet the first level standard of KS D 2042. Besides, welding defects were not occurred. The tensile strengths of the specimens using the filler metals of Al7075 and ER5356 had 240MPa and 252MPa, respectively. The yield strengths were 132MPa and 120MPa, respectively. In case of using the filler metal of Al7075, However, in case of using the filler metal of ER5356, Two filler metals of Al7075 and ER5356 were similar to each other in tensile and yield strength.

가스 터빈은 기동 및 정지 횟수가 많기 때문에 열피로나 취화 현상으로 인한 가스터빈 케이싱의 균열 또는 케이싱의 플랜지면에서 고온고압 가스의 누설이 발생할 가능성이 높다. 따라서 가스터빈 케이싱의 구조안전성 및 플랜지면에서의 누설평가는 반드시 수행되어야 하는 부분이다. 본 논문에서는 유한요소해석을 바탕으로 터빈 케이싱의 ASME B&PVC VIII-2 구조안전성 평가 및 접촉압력을 통한 누설 평가 그리고 볼트의 구조안전성 평가를 진행하였다. 또한 가스터빈 케이싱의 유한요소모델링 및 해석/평가 방법을 제안하여 가스터빈 개발에 활용할 수 있게 하였다.

가스 터빈은 기동 및 정지 횟수가 많기 때문에 열피로나 취화 현상으로 인한 가스터빈 케이싱의 균열 또는 케이싱의 플랜 지면에서 고온고압 가스의 누설이 발생할 가능성이 높다. 따라서 가스터빈 케이싱의 구조안전성 및 플랜지면에서의 누설평 가는 반드시 수행되어야 하는 부분이다. 본 논문에서는 유한요소해석을 바탕으로 터빈 케이싱의 ASME B&PVC VIII-2 구 조안전성 평가 및 접촉압력을 통한 누설 평가 그리고 볼트의 구조안전성 평가를 진행하였다. 또한 가스터빈 케이싱의 유한 요소모델링 및 해석/평가 방법을 제안하여 가스터빈 개발에 활용할 수 있게 하였다.

본 논문에서는 노심용융사고 시 관통노즐이 제거된 원자로용기 하부헤드의 구조 건전성 평가를 수행하였다. 열응력, 노심용융물의 질량 그리고 내압조건의 해석결과를 고려할 때, 하부헤드의 열응력에 의한 영향이 가장 크게 나타났다. 손상 가능성은 파손기준에 따라 평가하였으며, 등가소성변형률이 임계변형률 파손기준보다 낮은 수준으로 평가되었다. 열-구조물 연성해석 결과 하부헤드의 두께 중간층에서 항복강도보다 낮은 응력이 발생한 탄성영역 구간을 확인하였다. 내압이 커지면서 탄성영역 범위가 점차 좁아지면서 탄성영역이 내벽으로 이동하는 결과를 확인하였고, 노심용융사고 시 구조적 건전성을 만족하는 것으로 평가되었다.

In this paper, the necessity of developing effective nondestructive testing and monitoring techniques for the evaluation of structural integrity and performance is described. The evaluation of structural integrity and performance is especially important when the structures and subject to abrupt external forces such as earthquake. A prompt and extensive inspection is required over a large area of earthquake-damaged zone. This evaluation process is regarded as a part of performance-based design. In the paper, nondestructive testing and monitoring techniques particularly for concrete structures are presented as methods for the evaluation of structural integrity and performance. The concept of performance-based design is first defined in the paper followed by the role of evaluation of structures in the context of overall performance=based design concept. Among possible techniques for the evaluation, nondestructive testing methods for concrete structures using radar and a concept of using fiber sensor for continuous monitoring of structures are presented.

본 논문에서는 가압열충격의 파괴역학적 해석에 필요한 이론을 조사하였고 원자로용기의 구조건전성을 평가하기 위하여 해석과정을 전산화하였다. 우선 사고 transient에 대하여 원자로용기내의 압력과 주입되는 냉각재의 온도변화가 주어지면 이들로 부터 시간에 따른 용기에서의 온도와 응력분포를 구하고, 중성자 조사량과 용기 재질의 화학성분으로 부터 기준무연성천이온도의 분포가 구해지며 이로부터 파괴인성치 KIA와 KIC의 분포가 얻어진다. 또한 응력분포로 부터 균열의 크기 및 형상에 따라 응력확대계수 KI이 구해지므로 이를 KIA및 KIC와 비교함으로써 균열의 성장거동을 예측할 수 있다. 지금까지 보고된 가압열충격을 유발할 수 있는 대표적인 사고 transient가 국내 발전소에 발생할 경우를 가정하여 해석을 수행하였고 그 결과에 대하여 검토하였다.

The operation time of a disposal repository is generally more than one hundred years except for the institutional control phase. The structural integrity of a repository can be regarded as one of the most important research issues from the perspective of a long-term performance assessment, which is closely related to the public acceptance with regard to the nuclear safety. The objective of this study is to suggest the methodology for quantitative evaluation of structural integrity in a nuclear waste repository based on the adaptive artificial intelligence (AI), fractal theory, and acoustic emission (AE) monitoring. Here, adaptive AI means that the advanced AI model trained additionally based on the expert’s decision, engineering & field scale tests, numerical studies etc. in addition to the lab. test. In the process of a methodology development, AE source location, wave attenuation, the maximum AE energy and crack type classification were subsequently studied from the various lab. tests and Mazars damage model. The developed methodology for structural integrity was also applied to engineering scale concrete block (1.3 m × 1.3 m × 1.3 m) by artificial crack generation using a plate jacking method (up to 30 MPa) in KURT (KAERI Underground Research Tunnel). The concrete recipe used in engineering scale test was same as that of Gyeongju low & intermediate level waste repository. From this study, the reliability for AE crack source location, crack type classification, and damage assessment increased and all the processes for the technology development were verified from the Korea Testing Laboratory (KTL) in 2022.

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.

On-site storage facility using concrete silo dry storage systems for spent nuclear fuel at Wolsong NPP site came into operation in 1992 and was expanded four times, and a total of 300 silo dry storage systems are currently in operation. The design lifetime of silo dry storage systems has been licensed for 50 years. As the dry storage systems are subject to time constraints for a limited lifetime, countries operating the dry storage systems are working to ensure the long-term integrity of dry storage systems and IAEA also recommends that the dry storage systems be assessed for long-term storage. To demonstrate the long-term integrity due to material degradation during the licensed design lifetime, the structural integrity of silo dry storage systems was evaluated by considering the material degradation characteristics of concrete. The concrete compressive strength results measured so far by the rebound hammer method, which is an internationally standardized nondestructive test method for converting hardness into compressive strength using the correlation between rebound number and strength at the time of a Schmidt hammer strike, were analyzed in accordance with Wolsong NPP’s procedure to quantify the degradation characteristics, and the prediction of concrete strengths for 20 years and 50 years after construction of the silo dry storage systems was determined, respectively. Based on these residual compressive strengths, structural analyses of the silo dry storage systems were carried out under normal, off-normal and accident conditions of the related regulations, and the structural integrity of silo dry storage systems was reevaluated. It was confirmed the silo dry storage systems are able to maintain structural integrity up to the design lifetime of 50 years even if the concrete is deteriorated.