• 제목/요약/키워드: Core Damage

검색결과 442건 처리시간 0.037초

유한요소 해석을 이용한 동피복 복합선재의 인발 공정 해석 (Analysis of Copper clad steel wire in the drawing process using FE method)

  • 김현수;조훈;조형호;김대근;김병민
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2004년도 춘계학술대회 논문집
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    • pp.27-30
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    • 2004
  • Clad wire , which has the advantages of the high strength of a steel core and the electro-conductivity, corrosion resistance of a copper layer, is widely being used the telecommunications, electric-electronic and military technology industries, among others. It is important to obtain uniform coated rate when producing clad wires. Clad wire drawing process can be influenced on damage and coated rate of core and sleeve by process variables as semi-die angle and reduction in area. Therefore, in this study, the finite-element results established in previous study is used to analyze the effect of the various forming parameters, which included the semi-die angle, reduction in area etc. The coated rate will be predicted with observation copper coated rate variation according to total reduction in area and the optimal pass schedule will be set up through proper reduction in area and semi-die angle variation.

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필댐 보수보강후 시간경과에 따른 효과 분석 (Effect analysis by time passage after Repair & Reinforcement of Fill Dams)

  • 김재홍;오병현;임은상;홍원표
    • 한국지반공학회:학술대회논문집
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    • 한국지반공학회 2008년도 춘계 학술발표회 초청강연 및 논문집
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    • pp.697-703
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    • 2008
  • Excessive water leakage phenomenon happens through damage of nation core zone of about 17,000 storage of water facilities or collapse of dam is worried, is being damaged or enforce dilapidated fill dam core zone's repair reinforcement. Example that use grouting method of construction considering construction and economic performance etc. recently by repair reinforcement way about defect of dam is increased. Permeation grouting method repair & reinforcement of fill dam countermeasure is preferred in nation. Do that is economical to decide these repair reinforcement effect and grouting effect estimation method that do not give damage to dam is effective. Therefore, observing electricity resistivity Survey change of dam since grouting reinforcement using Electric resistivity Survey inquiry of seismic survey method in this research, Wished to verify grouting effect whether is possible as Electric resistivity Survey, and study whether integrity of dam through repair reinforcement defined.

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강봉댐퍼로 보강한 기존 저층 철근콘크리트 필로티 건물의 내진성능 (Seismic Performance of an Existing Low-Rise Reinforced Concrete Piloti Building Retrofitted by Steel Rod Damper)

  • 백은림;오상훈;이상호
    • 한국지진공학회논문집
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    • 제18권5호
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    • pp.241-251
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    • 2014
  • In this study, shaking table test was carried out to evaluate the seismic behavior and performance of low-rise reinforced concrete (RC) piloti structures with and without retrofit. The specimens were designed considering the characteristics of existing building with pilotis such as natural period, distribution factor of strength and stiffness between columns and core wall on the first soft story. The test for the non-retrofit specimen showed that damage was concentrated on the stiffer member on the same floor as the core wall failed by shear fracture whereas columns experienced slight flexural cracks. Considering the failure mode of the non-retrofit specimen, the retrofit method using steel rod damper was presented for improving the seismic performance of piloti structures. The results of the test for retrofit specimen revealed that the retrofit method was effective for controlling the damage as the main RC structural members were not destroyed and most of input energy was dissipated by hysteretic behavior of the damper.

APR+ 확률론적 안전성평가 및 대형냉각재상실사고 성공기준과 파단크기 민감도 분석 (A Study on the Probabilistic Safety Assessment and Sensitivity Analysis of Success Criteria of Large LOCA for APR+)

  • 문호림;김한곤
    • 한국안전학회지
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    • 제31권6호
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    • pp.129-134
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    • 2016
  • Standard design of APR+(advanced power reactor plus) was certified at 2014 by Korea regulatory body. Based on the experience gained from OPR1000 and APR1400, the APR1400 was being developed as a 1,500MWe class reactor using Korean technologies for design code, reactor coolant pump, and man-machine interface system. APR+ has been basically designed to have the seismic design basis of safe shutdown earthquake (SSE) 0.3g, a 4-train safety concept based on N+2 design philosophy, and a passive auxiliary feedwater system (PAFS). Also, safety issues on the Fukushima-type accidents have been extensively reviewed and applied to enhance APR+ safety. APR+ provides higher reliability and safety against tsunami and earthquake. The purpose of this paper is to implement probabilistic safety assessment considering these design features and to analyze sensitivity of core damage frequency for large loss of coolant accident of APR+.

PWR Hot Leg Natural Circulation Modeling with MELCOR Code

  • Park, Jae-Hong;Lee, Jong-In;Randall. K. Cole;Randall. O. Gauntt
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 추계학술발표회논문집(1)
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    • pp.772-777
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    • 1997
  • Previous MELCOR and SCDAP/RELAP5 nodalizations for simulating the counter-current, natural circulation behavior of vapor flow within the RCS hot legs and SG U-tubes when core damage progress can not be applied to the steady state and water-filled conditions during the initial period of accident progression because of the artificially high loss coefficients in the hot legs and SG U-tubes which were chosen from results of COMMIX calculation and the Westinghouse natural circulation experiments in a 1/7-scale facility for simulating steam natural circulation behavior in the vessel and in the hot leg and SG during the TMLB' scenrio. The objective of this study is to develop a natural circulation modeling which can be used both for the liquid flow condition at steady state and for the vapor flow condition at the later period of in-vessel core damage. For this, the drag forces resulting from the momentum exchange effects between the two vapor streams in the hot leg was modeled as a pressure drop by pump model. This hot leg natural circulation modeling of MELCOR was able to reproduce similar mass flow rates with those predicted by previous models.

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피동형 경수로 자동감압계통의 개선에 관한 연구 (Design Enhancements of Automatic Depressurization System in a Passive PWR)

  • Yu, Sung-Sik;Seong, Poong-Hyun
    • Nuclear Engineering and Technology
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    • 제25권4호
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    • pp.515-528
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    • 1993
  • 피동형 원자력 발전소의 설계 특성상 소형 냉각재상실사고시 노심손상이 발생되지 않기 위해서는 자동감압계통의 성공적인 작동이 필수적으로 요구된다. 그러나 기수행된 연구들에서 자동감압계통의 비신뢰도가 소형 냉각재상실사고로부터 기인되는 노심손상빈도에 상당 부분을 기여하고 있음을 알 수 있다. 본 연구에서는 자동감압계통의 불능도에 기여하는 계통의 취약점을 파악함과 함께 계통의 신뢰도를 증대시키기 위한 설계개선 방안들을 제시하고 각 방안에 대한 신뢰도 분석과 함께 열수력학적 타당성 여부를 보기 위한 소형 냉각재상실사고 모의가 RELAP5/MOD3 전산 코드를 사용하여 수행되었다. 신뢰도 분석은 고장수목 기법을 이용하여 수행되어졌다.

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Technical note: Estimation of Korean industry-average initiating event frequencies for use in probabilistic safety assessment

  • Kim, Dong-San;Park, Jin Hee;Lim, Ho-Gon
    • Nuclear Engineering and Technology
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    • 제52권1호
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    • pp.211-221
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    • 2020
  • One fundamental element of probabilistic safety assessment (PSA) is the initiating event (IE) analysis. Since IE frequencies can change over time, time-trend analysis is required to obtain optimized IE frequencies. Accordingly, such time-trend analyses have been employed to estimate industry-average IE frequencies for use in the PSAs of U.S. nuclear power plants (NPPs); existing PSAs of Korean NPPs, however, neglect such analysis in the estimation of IE frequencies. This article therefore provides the method for and results of estimating Korean industry-average IE frequencies using time-trend analysis. It also examines the effects of the IE frequencies obtained from this study on risk insights by applying them to recently updated internal events Level 1 PSA models (at-power and shutdown) for an OPR-1000 plant. As a result, at-power core damage frequency decreased while shutdown core damage frequency increased, with the related contributions from each IE category changing accordingly. These results imply that the incorporation of time-trend analysis leads to different IE frequencies and resulting risk insights. The IE frequency distributions presented in this study can be used in future PSA updates for Korean NPPs, and should be further updated themselves by adding more recent data.

Analysis of rectangular hybrid steel-GFRP reinforced concrete beam columns

  • El-Heloua, Rafic G.;Aboutaha, Riyad S.
    • Computers and Concrete
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    • 제16권2호
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    • pp.245-260
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    • 2015
  • In this study, nominal moment-axial load interaction diagrams, moment-curvature relationships, and ductility of rectangular hybrid beam-column concrete sections are analyzed using the modified Hognestad concrete model. The hybrid columns are primarily reinforced with steel bars with additional Glass Fiber Reinforced Polymer (GFRP) control bars. Parameters investigated include amount, pattern, location, and material properties of concrete, steel, and GFRP. The study was implemented using a user defined comprehensive $MATLAB^{(R)}$ simulation model to find an efficient hybrid section design maximizing strength and ductility. Generating lower bond stresses than steel bars at the concrete interface, auxiliary GFRP bars minimize damage in the concrete core of beam-column sections. Their usage prevents excessive yielding of the core longitudinal bars during frequent moderate cyclic deformations, which leads to significant damage in the foundations of bridges or beam-column spliced sections where repair is difficult and expensive. Analytical results from this study shows that hybrid steel-GFRP composite concrete sections where GFRP is used as auxiliary bars show adequate ductility with a significant increase in strength. Results also compare different design parameters reaching a number of design recommendations for the proposed hybrid section.

Variability of plant risk due to variable operator allowable time for aggressive cooldown initiation

  • Kim, Man Cheol;Han, Sang Hoon
    • Nuclear Engineering and Technology
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    • 제51권5호
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    • pp.1307-1313
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    • 2019
  • Recent analysis results with realistic assumptions provide the variability of operator allowable time for the initiation of aggressive cooldown under small break loss of coolant accident or steam generator tube rupture with total failure of high pressure safety injection. We investigated how plant risk may vary depending on the variability of operators' failure probability of timely initiation of aggressive cooldown. Using a probabilistic safety assessment model of a nuclear power plant, we showed that plant risks had a linear relation with the failure probability of aggressive cooldown and could be reduced by up to 10% as aggressive cooldown is more reliably performed. For individual accident management, we found that core damage potential could be gradually reduced by up to 40.49% and 63.84% after a small break loss of coolant accident or a steam generator tube rupture, respectively. Based on the importance of timely initiation of aggressive cooldown by main control room operators within the success criteria, implications for improvement of emergency operating procedures are discussed. We recommend conducting further detailed analyses of aggressive cooldown, commensurate with its importance in reducing risks in nuclear power plants.

Interface monitoring of steel-concrete-steel sandwich structures using piezoelectric transducers

  • Yan, Jiachuan;Zhou, Wensong;Zhang, Xin;Lin, Youzhu
    • Nuclear Engineering and Technology
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    • 제51권4호
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    • pp.1132-1141
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    • 2019
  • Steel-concrete-steel (SCS) sandwich structures have important advantages over conventional concrete structures, however, bond-slip between the steel plate and concrete may lead to a loss of composite action, resulting in a reduction of stiffness and fatigue life of SCS sandwich structures. Due to the inaccessibility and invisibility of the interface, the interfacial performance monitoring and debonding detection using traditional measurement methods, such as relative displacement between the steel plate and core concrete, have proved challenging. In this work, two methods using piezoelectric transducers are proposed to detect the bond-slip between steel plate and core concrete during the test of the beam. The first one is acoustic emission (AE) method, which can detect the dynamic process of bond-slip. AE signals can be detected when initial micro cracks form and indicate the damage severity, types and locations. The second is electromechanical impedance (EMI) method, which can be used to evaluate the damage due to bond-slip through comparing with the reference data in static state, even if the bond-slip is invisible and suspends. In this work, the experiment is implemented to demonstrate the bond-slip monitoring using above methods. Experimental results and further analysis show the validity and unique advantage of the proposed methods.