• Title/Summary/Keyword: Drop Impact Analysis

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Integrity of the Reactor Vessel Support System for a Postulated Reactor Vessel Closure Head Drop Event

  • Kim, Tae-Wan;Lee, Ki-Young;Lee, Dae-Hee;Kim, Kang-Soo
    • Nuclear Engineering and Technology
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    • v.28 no.6
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    • pp.576-582
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    • 1996
  • The integrity of reactor vessel support system of the Korean Standard Nuclear Power Plant (KSNPP) is investigated for a postulated reactor vessel closure head drop event. The closure head is disassembled from the reactor vessel during refueling process or general inspection of reactor vessel and internal structures, and carried to proposed location by the head lift rig. A postulated closure head drop event could be anticipated during closure head handling process. The drop event may cause an impact load on the reactor vessel and supporting system. The integrity of the supporting system is directly relevant to that of reactor vessel and reactor internals including fuels. Results derived by elastic impact analysis, linear and non-linear buckling analysis and elasto-plastic stress analysis of the supporting system implied that the integrity of the reactor vessel supporting system is intact for a postulated reactor vessel closure head drop event.

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Shock Resistance Characteristic of Auto Focus Actuator using Finite Element Method and Drop Impact Test (유한요소해석과 낙하충격 실험을 통한 자동초점 액추에이터의 내충격 특성 향상)

  • Shin, Min-Ho;Kim, Hyo-Jun;Park, Gyusub;Kim, Young-Joo
    • Transactions of the Society of Information Storage Systems
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    • v.9 no.2
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    • pp.56-61
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    • 2013
  • The recent increased use of mobile phone has resulted in a technical focusing on reliability issues related to drop performance. Since mobile phone may be dropped several times during their use, it is required to survive common drop accidents. The plastic injection parts such as base stopper and carrier in the encoder type actuator can be broken easily in the actual reliability test of 1.5m free drop. So, we analyzed the shock resistance characteristics of auto focus actuator with variables in the material properties using finite element method. By applying the new resin materials, we can decrease the breakage of plastic injection parts and improve the reliability of mobile phone.

Numerical Study of Drop/impact test and Shock/impact Survivability Test for ELT(Emergency Locator Transmitter) Operations (ELT(Emergency Locator Transmitter) 운용을 위한 낙하 충격 및 추락생존성 시험에 대한 수치 해석적 연구)

  • Jung, Do-Hee;Baek, Jong-Jin
    • Journal of the Korean Society for Aeronautical & Space Sciences
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    • v.36 no.12
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    • pp.1229-1235
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    • 2008
  • ELT(emergency locator transmitter) has assisted in the rescue of thousands of lives in distress. Aviators, mariners and land users being equipped with distress beacons are capable of transmitting distress signals to the satellites in emergency situations anywhere in the world. In this paper, Drop/Impact simulation was performed for ELT Body-case. FE model for Body-case was constructed with MSC/Dytran and refined using the Karas example simulation for Body-case prototype. Shock/impact survivability analysis was performed for ELT operations. FE model constructed with MSC/Nastran. Transient response analysis for refined ELT model was perfomed for ELT under impact shock loading condition.

Numerical estimation of errors in drop angle during drop tests of IP-Type metallic transport containers for radioactive materials

  • Lim, Jongmin;Yang, Yun Young;Lee, Ju-chan
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.1878-1886
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    • 2021
  • For industrial package (IP)-type transport containers for radioactive materials, a free drop test should be conducted under regulatory conditions. Owing to various uncertainties observed during the drop test, errors in drop angles inevitably occur. In IP-type metal transport containers in which the container directly impacts onto a rigid target without any shock absorbing materials, the error in the drop angle due to a slight misalignment makes a significant difference from the ideal drop. In particular, in a vertical drop, the error in the drop angle causes a strong secondary impact. In this paper, a numerical method is proposed to estimate the error in the drop angle occurring during the test. To determine this error, an optimization method accompanying a computational drop analysis is proposed, and a surrogate model is introduced to ensure calculation efficiency. Effectiveness of the proposed method is validated by performing the verification and comparison between the test and the analysis applied with the drop angle error.

Integrity Evaluation of Control Rod Assembly for Sodium-Cooled Fast Reactor due to Drop Impact (낙하충격에 의한 소듐냉각고속로 제어봉집합체의 건전성 평가)

  • Lee, Hyun Seung;Yoon, Kyung Ho;Kim, Hyung Kyu;Cheon, Jin Sik;Lee, Chan Bock
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.41 no.3
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    • pp.233-239
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    • 2017
  • The CA (Control Assembly) of an SFR has a CRA(Control Rod Assembly) with an inner duct and control rod. During an emergency situation, the CRA falls into the duct of the CA for a rapid shut-down. The drop time and impact velocity of the CRA are important parameters with respect to the reactivity insertion time and the structural integrity of the CRA. The objective of this study was to investigate the dynamic behavior and integrity of the CRA owing to a drop impact. The impact analysis of the CRA under normal/abnormal drop conditions was carried out using the commercial FEM code LS-DYNA. Results of the drop impact analysis demonstrated that the CRA maintained structural integrity, and could be safely inserted into the flow hole of the damper under abnormal conditions.

CFD Analysis to Estimate Drop Time and Impact Velocity of a Control Rod Assembly in the Sodium Cooled Faster Reactor (소듐냉각고속로 제어봉집합체의 낙하시간 및 충격속도 예측을 위한 CFD 해석)

  • Kim, JaeYong;Yoon, KyungHo;Oh, Se-Hong;Ko, SungHo
    • The KSFM Journal of Fluid Machinery
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    • v.18 no.6
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    • pp.5-11
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    • 2015
  • In a pressurized water reactor (PWR), control rod assembly (CRA) falls into the guide tubes of a fuel assembly due to gravity for scram. Various theoretical approaches and numerical analyses have been performed because its shape is simple and its design was completely developed several decades ago. A control rod assembly for a sodium-cooled faster reactor (SFR) which is geometrically more complicated is being actively developed in Korea nowadays. Drop time and impact velocity of a CRA are important parameters with respect to reactivity insertion time and the mechanical robustness of a CRA and a guide duct. In this paper, computational method considering simultaneously the equation of motion for rigid body and the Navier-Stokes equations for fluid is suggested and verified by comparison with theoretical analysis results. Through this valuable CFD analysis method, drop time and impact velocity of initially designed SFR CRA are evaluated before performing scram tests with it.

Drop Analysis of a Package and Cushion Performance of Drum Washing Machine (드럼 세탁기 포장재 낙하해석 및 완충 특성)

  • Kim, Chang-Sub;Bae, Bong-Kook;Sung, Do-Young
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.34 no.11
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    • pp.1733-1740
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    • 2010
  • The analysis of the dynamic behavior of the packaging of a drum washing machine has been carried out under the drop impact conditions. LS-DYNA software is used for performing the finite element analysis, and the validations are performed by comparing with the impact acceleration, effective stress and deformation of cushioned package with high-speed camera during free drop test. By analyzing the cushion characteristics and the design parameters of the original packaging, a packaging with an improved design is developed, and this design is validated on the basis of the results of the distribution test which consists of drop test, vibration test, stacking test, squeez test and so on. The drop impact simulation and analysis methods developed in this study can be adopted to successfully improve the cushioning provided by the packaging and to reduce the cost involved in developing new packaging for drum washing machines.

A study on the impact pulse analysis with various shapes and materials of impactor (충격자의 형상 및 재질변화에 따른 펄스형성에 관한 연구)

  • Lee, Yeong-Sin;Kim, Dong-Jin;Gang, Geun-Hui;O, Jong-Su
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.22 no.1
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    • pp.52-63
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    • 1998
  • The impact programmer for impact test was designed and the impact analysis was conducted. The effects of the material and geometric parameters on the impact force and pulse shape were investigated. The impact characteristics were examined by experimental and finite element method. The impact test was conducted with free drop impact tester. The ABAQUS/Explicit 5.5 version was used for finite element analysis. The geometric parameters of the conical and dome type impact programmer were analyzed. The polyurethane impact programmers were fabricated and tested. The effects of the hardness and thickness of the impact programmer were studied. The peak acceleration and time duration of impact programmer have close correlation with the hardness, impact energy and thickness of the impactor. The experiment was good agreement with analytical predictions. The impact pulse shape generated with polyurethane impact programmer was half sine shape. The maximum impact force was proportional to impact energy. The impact acceleration was decreased with thickness of impact programmer. The maximum impact time duration level was about 2 msec.

Study on the Impact-proof Internal Structure Design of a Spent Nuclear Fuel Transport Cask (내충격성을 고려한 사용후연료 수송용기 내부구조물의 설계 연구)

  • Shin, Tae-Myung;Kim, Kap-Sun
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.19 no.4
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    • pp.370-377
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    • 2009
  • A simple preliminary analysis is often useful to check a validity of design alternatives before the detailed analysis phase in the viewpoint of efficiency. This paper describes a preliminary analysis procedure for the selection among basket design candidates for the spent fuel shipping cask of Korean standard nuclear power plant. As the cask should maintain the structural integrity in hypothetical accident condition, the case of 9 m drop is significantly considered as the worst scenario among the accident conditions in structural design viewpoint in this paper. As basket design options, totally four different types are considered and analyzed in the point of structural integrity at drop impact and weldability for fabrication. As a result, an insertion round plate type with densely spaced supports turns out to be the best in both of the viewpoints, though the weld plate type shows a bit more design margin.