• Title/Summary/Keyword: Safety Integrity

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A Study on Reinforcement Method of Concrete Block for Direct Fixation Tracks on Serviced Light Rail Transit (공용중인 경전철 직결 궤도 콘크리트 도상블록의 보강 방안 연구)

  • Jung-Youl Choi;You-Song Kang;Dae-Hee Ahn;Jae-Min Han;Jee-Seung Chung
    • The Journal of the Convergence on Culture Technology
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    • v.9 no.3
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    • pp.633-640
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    • 2023
  • In this study, numerical analysis was performed based on field investigation to derive an appropriate reinforcement method by analyzing the displacement behavior characteristics of concrete blocks generated in the direct fixation track on the bridges of the serviced light rail transit. The track of this study was a direct fixation track on a sharp curved track, and the problem of movement of the concrete blocks installed on the bridge deck in the longitudinal and lateral directions occurred. In this study, based on the finite element model using 3D solid elements, the behavior of the direct fixation track that could be occurred under operating load conditions was analyzed. In addition, the reinforcement effect of various reinforcement methods was analyzed. As a result of analyzing the lateral displacement before and after reinforcement, it was analyzed that the maximum lateral displacement after reinforcement under the extreme lateral wheel loads significantly decreased to about 3% (about 0.1mm) compared to before reinforcement. In addition, as a result of examining the generated stress of the filling mortar, bridge decks, and reinforcing bar, it was analyzed that all of them secured a sufficient safety factor of 2.6 or higher, and the optimal conditions for the reinforcement method were derived. Therefore, it is judged that the number of anchoring reinforcements and symmetrical anchor placement reviewed in this study will be effective in controlling the occurrence of lateral displacement of concrete blocks and securing the structural integrity of bridges and concrete blocks.

ESG Management Strategy and Performance Management Plan Suitable for Social Welfare Institutions : Centered on Cheonan City Social Welfare Foundation (사회복지기관에 적합한 ESG경영 전략도출 및 성과관리방안 : 천안시사회복지재단을 중심으로)

  • Hwang, Kyoo-il
    • Journal of Venture Innovation
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    • v.6 no.3
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    • pp.165-184
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    • 2023
  • Since municipal welfare institutions operate for different purposes from general companies or public enterprises, ESG practice items and model construction should be conducted through various and comprehensive social welfare studies. Since there are not many studies available in domestic welfare institutions yet and there are no suitable ESG management utilization indicators, the Cheonan Welfare Foundation's strategy and management strategy system were established to spread the model to other welfare institutions and become a leading foundation through education and training. The foundation and front-line welfare institutions selected issues identification and key issues through the foundation's empirical analysis and criticality analysis, focusing on understanding ESG management and ways to establish a practice model that positively affects institutional image and business performance. Based on this, the promotion system was examined by establishing a performance management plan after deriving appropriate strategies and establishing a strategic system for social welfare institutions. Environmental and social responsibility, transparent management, safety management system establishment, emergency and prevention, user (customer) satisfaction system establishment, anti-corruption prevention and integrity ethics monitoring and evaluation, responsible supply chains, and community contribution programs. This study attempted to specifically present efforts to settle ESG management through the consideration of the Cheonan Welfare Foundation. Therefore, it is considered to be useful data for developing ESG management by referring to the systematic development process of the Cheonan City Restoration Foundation to develop ESG measurement indicators.

Case Study of Deep Geological Disposal Facility Design for High-level Radioactive Waste (스웨덴 고준위방사성폐기물 심층처분시설의 설계 사례 분석)

  • Juhyi Yim;Jae Hoon Jung;Seokwon Jeon;Ki-Il Song;Young Jin Shin
    • Tunnel and Underground Space
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    • v.33 no.5
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    • pp.312-338
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    • 2023
  • The underground disposal facility for spent nuclear fuel demands a specialized design, distinct from conventional practices, to ensure long-term thermal, mechanical, and hydraulic integrity, preventing the release of radioactive isotopes from high-temperature spent nuclear fuel. SKB has established design criteria for such facilities and executed practical design implementations for Forsmark. Moreover, in response to subsurface uncertainty, SKB has proposed an empirical approach involving monitoring and adaptive design modifications, alongside stepwise development. SKB has further introduced a unique support system, categorizing ground types and behaviors and aligning them with corresponding support types to confirm safety through comparative analyses against existing systems. POSIVA has pursued a comparable approach, developing a support system for Onkalo while accounting for distinct geological characteristics compared to Forsmark. This demonstrates the potential for domestic implementation of spent nuclear fuel disposal facility designs and the establishment of a support system adapted to national attributes.

Application of Back Analysis Technique Based on Direct Search Method to Estimate Tension of Suspension Bridge Hanger Cable (현수교 행어케이블의 장력 추정을 위한 직접탐색법 기반의 역해석 기법의 적용 )

  • Jin-Soo Kim;Jae-Bong Park;Kwang-Rim Park;Dong-Uk Park;Sung-Wan Kim
    • Journal of the Korea institute for structural maintenance and inspection
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    • v.27 no.5
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    • pp.120-129
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    • 2023
  • Hanger cable tension is a major response that can determine the integrity and safety of suspension bridges. In general, the vibration method is used to estimate hanger cable tension on operational suspension bridges. It measures natural frequencies from hanger cables and indirectly estimates tension using the geometry conditions of the hanger cables. This study estimated the hanger cable tension of the Palyeong Bridge using a vision-based system. The vision-based system used digital camcorders and tripods considering the convenience and economic efficiency of measurement. Measuring the natural frequencies for high-order modes required for the vibration method is difficult because the hanger cable response measured using the vision-based system is displacement-based. Therefore, this study proposed a back analysis technique for estimating tension using the natural frequencies of low-order modes. Optimization for the back analysis technique was performed by defining the difference between the natural frequencies of hanger cables measured in the field and those calculated using finite element analysis as the objective function. The direct search method that does not require the partial derivatives of the objective function was applied as the optimization method. The reliability and accuracy of the back analysis technique were verified by comparing the tension calculated using the method with that estimated using the vibration method. Tension was accurately estimated using the natural frequencies of low-order modes by applying the back analysis technique.

Mechanical behavior of 316L austenitic stainless steel bolts after fire

  • Zhengyi Kong;Bo Yang;Cuiqiang Shi;Xinjie Huang;George Vasdravellis;Quang-Viet Vu;Seung-Eock Kim
    • Steel and Composite Structures
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    • v.50 no.3
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    • pp.281-298
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    • 2024
  • Stainless steel bolts (SSB) are increasingly utilized in bolted steel connections due to their good mechanical performance and excellent corrosion resistance. Fire accidents, which commonly occur in engineering scenarios, pose a significant threat to the safety of steel frames. The post-fire behavior of SSB has a significant influence on the structural integrity of steel frames, and neglecting the effect of temperature can lead to serious accidents in engineering. Therefore, it is important to evaluate the performance of SSB at elevated temperatures and their residual strength after a fire incident. To investigate the mechanical behavior of SSB after fire, 114 bolts with grades A4-70 and A4-80, manufactured from 316L austenitic stainless steel, were subjected to elevated temperatures ranging from 20℃ to 1200℃. Two different cooling methods commonly employed in engineering, namely cooling at ambient temperatures (air cooling) and cooling in water (water cooling), were used to cool the bolts. Tensile tests were performed to examine the influence of elevated temperatures and cooling methods on the mechanical behavior of SSB. The results indicate that the temperature does not significantly affect the Young's modulus and the ultimate strength of SSB. Up to 500℃, the yield strength increases with temperature, but this trend reverses when the temperature exceeds 500℃. In contrast, the ultimate strain shows the opposite trend. The strain hardening exponent is not significantly influenced by the temperature until it reaches 500℃. The cooling methods employed have an insignificant impact on the performance of SSB. When compared to high-strength bolts, 316L austenitic SSB demonstrate superior fire resistance. Design models for the post-fire mechanical behavior of 316L austenitic SSB, encompassing parameters such as the elasticity modulus, yield strength, ultimate strength, ultimate strain, and strain hardening exponent, are proposed, and a more precise stress-strain model is recommended to predict the mechanical behavior of 316L austenitic SSB after a fire incident.

Effect of the initial imperfection on the response of the stainless steel shell structures

  • Ali Ihsan Celik;Ozer Zeybek;Yasin Onuralp Ozkilic
    • Steel and Composite Structures
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    • v.50 no.6
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    • pp.705-720
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    • 2024
  • Analyzing the collapse behavior of thin-walled steel structures holds significant importance in ensuring their safety and longevity. Geometric imperfections present on the surface of metal materials can diminish both the durability and mechanical integrity of steel shells. These imperfections, encompassing local geometric irregularities and deformations such as holes, cavities, notches, and cracks localized in specific regions of the shell surface, play a pivotal role in the assessment. They can induce stress concentration within the structure, thereby influencing its susceptibility to buckling. The intricate relationship between the buckling behavior of these structures and such imperfections is multifaceted, contingent upon a variety of factors. The buckling analysis of thin-walled steel shell structures, similar to other steel structures, commonly involves the determination of crucial material properties, including elastic modulus, shear modulus, tensile strength, and fracture toughness. An established method involves the emulation of distributed geometric imperfections, utilizing real test specimen data as a basis. This approach allows for the accurate representation and assessment of the diversity and distribution of imperfections encountered in real-world scenarios. Utilizing defect data obtained from actual test samples enhances the model's realism and applicability. The sizes and configurations of these defects are employed as inputs in the modeling process, aiding in the prediction of structural behavior. It's worth noting that there is a dearth of experimental studies addressing the influence of geometric defects on the buckling behavior of cylindrical steel shells. In this particular study, samples featuring geometric imperfections were subjected to experimental buckling tests. These same samples were also modeled using Finite Element Analysis (FEM), with results corroborating the experimental findings. Furthermore, the initial geometrical imperfections were measured using digital image correlation (DIC) techniques. In this way, the response of the test specimens can be estimated accurately by applying the initial imperfections to FE models. After validation of the test results with FEA, a numerical parametric study was conducted to develop more generalized design recommendations for the stainless-steel shell structures with the initial geometric imperfection. While the load-carrying capacity of samples with perfect surfaces was up to 140 kN, the load-carrying capacity of samples with 4 mm defects was around 130 kN. Likewise, while the load carrying capacity of samples with 10 mm defects was around 125 kN, the load carrying capacity of samples with 14 mm defects was measured around 120 kN.

A comparison study of the characteristics of private and public security service of Koryo dynasty and modern security service (고려시대 공적·사적경호의 특성과 현대경호와의 비교연구)

  • Lee, Sung-Jin
    • Korean Security Journal
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    • no.36
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    • pp.417-442
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    • 2013
  • This study considers the characteristics of the separation of public and private security service during Koryo dynasty, and compares it with the modern security service. Modern day security service's definition of private and public security service was used to distinguish them. Given the different historical settings, it's difficult to argue that the distinction between public and private service during Koryo dynasty was clear, but it can be said that public security service was centered around palace guard and concerns the activities of protest, and military made for the relationship, and private security service was centered around power of DoBang and includes the activities of malingering, and Byolchogun. During the early days of Koryo, protest, district military and soldiers who stay in the palace were all parts of a palace revolt and this institutional improvement of soldiers who stay in the palace was accomplished during King Seongjong's rule. The tradition of a palace revolt can find its roots in the middle military, and after the unification, a palace revolt was reformed into the king's palace revolt of second and the 6th along the course of establishing the nation's system. All of the changes stem from the reformation for consolidating the royal authority. Gyung Dae Seoung wanted to protect himself and he slept with his army night and days and because of that, group of soldiers was created and it was called DOBANG. Some members were from dobang gyeonryong, The forced were powerful because it was gathered with a warriors with extraordinaire martial arts and competent management. Most of the soldiers followed gyeong dae seung because they believed that he has a strong leadership and loves his people, and had a strong faith in him. However, the general gyeong jang had a belief that politics must be reverted to the previous so the relationships between jungbang wasn't smooth. Because of the economic operational problems, due to fraud committed by the mens under his command failed to maintain integrity and was criticised.The misconception also fed up with the emperor and the deepening relationships between the soldiers, his dobang was dismantled. After he took over the dobang, for his personal safety and to strengthen his position he compensated gyeon dae seong's dobang and developed the organization. In the process of extending the dobang Choi chung heon recruited many talented people to strengthen the military base, and also accepted the advice and expanded the power of Dobang. Choi Chung Heon thus consolidated his political gains by weakening the power of the king's army and adjusting the myth, which could've threatened his regime, and this was called Dobang number 6th. Dobang number six got even more powerful by his son named Choi woo, and after ruling, he expanded into a room, and a substantial reorganization of Dobang was developed. And then the creation of yabyeolcho also showed the effect to prevent the crisis. Although the palace guards who were public security service of Koryo Dynasty was still maintained during the military rule era when the royal authority was incapacitated, it was only maintained to have a symbolic meaning as the actual authority including military power was with Choi, the master of Dobang, private security service group. Likewise, during the rule of Choi, private securty service could reign over public security service, and the noteworthy characteristic of Dobang is that it assisted the private soldier groups to seize the military power by reorganizing and modifying military system. Although both differences and similarities can be found when comparing the guards of Koryo Dynasty with those of contemporary society, they have a similarity in terms of the essence of guards that they guarantee the safety of their clients. As for differences, the royalty of Koryo Dynasty and the pursuit of profit of contemporary society are in contrast, and contemporary guards can be seen as the fulfillment of responsibility and duty by free will, whereas guards of Koryo Dynasty were ruled with military coercion.

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Commissioning Experience of Tri-Cobalt-60 MRI-guided Radiation Therapy System (자기공명영상유도 Co-60 기반 방사선치료기기의 커미셔닝 경험)

  • Park, Jong Min;Park, So-Yeon;Wu, Hong-Gyun;Kim, Jung-in
    • Progress in Medical Physics
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    • v.26 no.4
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    • pp.193-200
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    • 2015
  • The aim of this study is to present commissioning results of the ViewRay system. We verified safety functions of the ViewRay system. For imaging system, we acquired signal to noise ratio (SNR) and image uniformity. In addition, we checked spatial integrity of the image. Couch movement accuracy and coincidence of isocenters (radiation therapy system, imaging system and virtual isocneter) was verified. Accuracy of MLC positioing was checked. We performed reference dosimetry according to American Association of Physicists in Medicine (AAPM) Task Group 51 (TG-51) in water phantom for head 1 and 3. The deviations between measurements and calculation of percent depth dose (PDD) and output factor were evaluated. Finally, we performed gamma evaluations with a total of 8 IMRT plans as an end-to-end (E2E) test of the system. Every safety system of ViewRay operated properly. The values of SNR and Uniformity met the tolerance level. Every point within 10 cm and 17.5 cm radii about the isocenter showed deviations less than 1 mm and 2 mm, respectively. The average couch movement errors in transverse (x), longitudinal (y) and vertical (z) directions were 0.2 mm, 0.1 mm and 0.2 mm, respectively. The deviations between radiation isocenter and virtual isocenter in x, y and z directions were 0 mm, 0 mm and 0.3 mm, respectively. Those between virtual isocenter and imaging isocenter were 0.6 mm, 0.5 mm and 0.2 mm, respectively. The average MLC positioning errors were less than 0.6 mm. The deviations of output, PDDs between mesured vs. BJR supplement 25, PDDs between measured and calculated and output factors of each head were less than 0.5%, 1%, 1% and 2%, respectively. For E2E test, average gamma passing rate with 3%/3 mm criterion was $99.9%{\pm}0.1%$.

Activation Analysis of Dual-purpose Metal Cask After the End of Design Lifetime for Decommission (설계수명 이후 해체를 위한 금속 겸용용기의 방사화 특성 평가)

  • Kim, Tae-Man;Ku, Ji-Young;Dho, Ho-Seog;Cho, Chun-Hyung;Ko, Jae-Hun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.4
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    • pp.343-356
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    • 2016
  • The Korea Radioactive Waste Agency (KORAD) has developed a dual-purpose metal cask for the dry storage of spent nuclear fuel that has been generated by domestic light-water reactors. The metal cask was designed in compliance with international and domestic technology standards, and safety was the most important consideration in developing the design. It was designed to maintain its integrity for 50 years in terms of major safety factors. The metal cask ensures the minimization of waste generated by maintenance activities during the storage period as well as the safe management of the waste. An activation evaluation of the main body, which includes internal and external components of metal casks whose design lifetime has expired, provides quantitative data on their radioactive inventory. The radioactive inventory of the main body and the components of the metal cask were calculated by applying the MCNP5 ORIGEN-2 evaluation system and by considering each component's chemical composition, neutron flux distribution, and reaction rate, as well as the duration of neutron irradiation during the storage period. The evaluation results revealed that 10 years after the end of the cask's design life, $^{60}Co$ had greater radioactivity than other nuclides among the metal materials. In the case of the neutron shield, nuclides that emit high-energy gamma rays such as $^{28}Al$ and $^{24}Na$ had greater radioactivity immediately after the design lifetime. However, their radioactivity level became negligible after six months due to their short half-life. The surface exposure dose rates of the canister and the main body of the metal cask from which the spent nuclear fuel had been removed with expiration of the design lifetime were determined to be at very low levels, and the radiation exposure doses to which radiation workers were subjected during the decommissioning process appeared to be at insignificant levels. The evaluations of this study strongly suggest that the nuclide inventory of a spent nuclear fuel metal cask can be utilized as basic data when decommissioning of a metal cask is planned, for example, for the development of a decommissioning plan, the determination of a decommissioning method, the estimation of radiation exposure to workers engaged in decommissioning operations, the management/reuse of radioactive wastes, etc.

A Review of the Influence of Sulfate and Sulfide on the Deep Geological Disposal of High-level Radioactive Waste (고준위방사성폐기물 심층처분에 미치는 황산염과 황화물의 영향에 대한 고찰)

  • Jin-Seok Kim;Seung Yeop Lee;Sang-Ho Lee;Jang-Soon Kwon
    • Economic and Environmental Geology
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    • v.56 no.4
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    • pp.421-433
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    • 2023
  • The final disposal of spent nuclear fuel(SNF) from nuclear power plants takes place in a deep geological repository. The metal canister encasing the SNF is made of cast iron and copper, and is engineered to effectively isolate radioactive isotopes for a long period of time. The SNF is further shielded by a multi-barrier disposal system comprising both engineering and natural barriers. The deep disposal environment gradually changes to an anaerobic reducing environment. In this environment, sulfide is one of the most probable substances to induce corrosion of copper canister. Stress-corrosion cracking(SCC) triggered by sulfide can carry substantial implications for the integrity of the copper canister, potentially posing a significant threat to the long-term safety of the deep disposal repository. Sulfate can exist in various forms within the deep disposal environment or be introduced from the geosphere. Sulfate has the potential to be transformed into sulfide by sulfate-reducing bacteria(SRB), and this converted sulfide can contribute to the corrosion of the copper canister. Bentonite, which is considered as a potential material for buffering and backfilling, contains oxidized sulfate minerals such as gypsum(CaSO4). If there is sufficient space for microorganisms to thrive in the deep disposal environment and if electron donors such as organic carbon are adequately supplied, sulfate can be converted to sulfide through microbial activity. However, the majority of the sulfides generated in the deep disposal system or introduced from the geosphere will be intercepted by the buffer, with only a small amount reaching the metal canister. Pyrite, one of the potential sulfide minerals present in the deep disposal environment, can generate sulfates during the dissolution process, thereby contributing to the corrosion of the copper canister. However, the quantity of oxidation byproducts from pyrite is anticipated to be minimal due to its extremely low solubility. Moreover, the migration of these oxidized byproducts to the metal canister will be restricted by the low hydraulic conductivity of saturated bentonite. We have comprehensively analyzed and summarized key research cases related to the presence of sulfates, reduction processes, and the formation and behavior characteristics of sulfides and pyrite in the deep disposal environment. Our objective was to gain an understanding of the impact of sulfates and sulfides on the long-term safety of high-level radioactive waste disposal repository.