• Nuclear Engineering and Technology
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• 제27권3호
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• pp.418-426
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• 1995

설계의 신뢰성은 응력해석을 통하여 확인될 수 있으며, 해석결과는 대상 부품의 구조적 건전성을 입증하는 근거가 된다. 본 보고서는 ANSYS의 피로해석 모듈을 이용한 CANDU 6핵연료채널의 응력해석 및 ASME Code에 따른 해석 절차 개발을 소개하였다. 응력해석은 ASME Code Section III NB-3200 의 $\ulcorner$Design by Analysis$\lrcorner$에 기초한 해석절차에 따라 수행하였으며, 체계적인 해석을 위해 자료 처리용 ANSYS 매크로 및 FORTRAN 프로그램을 개발하였다. 해석은 각 조건에 따라 기계적응력과 열응력해석으로 분리하여 수행한 후 조합되었으며, ANSYS 피로해석 모듈을 이용하여 선정된 절점들의 기계적응력과 열응력의 합에 대한 최대응력강도범위를 계산하였다. 응력해석 결과, CANDU 6 핵연료채널의 구조적 건전성이 입증되었으며, ANSYS를 이용한 ASME Code해석절차가 확립되어 CANDU 원자로 해석의 신뢰성을 크게 향상 시켰음은 물론 독자적인 수행을 위한 발판을 마련하였다.

• 한국산업융합학회 논문집
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• 제25권6_2호
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• pp.1091-1095
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• 2022

Dynamic stability of the main spindle system shall be ensured when operating the planer miller for remanufacturing the planer miller. This paper explains the analysis process that determines the stability of the planer miller spindle system in the design stage using ANSYS, an analysis program. First, the dynamic stability of the main spindle system is verified through risk speed analysis in the rated RPM range of the planer miller through ANSYS Modal Analysis, and second, the stability and durability of the main spindle system are verified through ANSYS nCode Analysis.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.256.1-256
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• 1999

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
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• pp.1696-1699
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• 1997

The robot mainpulator for inspection of pressurizer in the nuclear power plant has been developed, which consists of four parts : 2 arms, movable gripper, base frame, contorl console. To extract the damaged electric heating rod inside pressurizer, the gripper has been developed using wire lope and self-locking mechanism. for the examination of the structural stability of the robot manipulator, stress analysis is performed by using the ANSYS code.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2007년도 추계학술대회논문집
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• pp.1366-1370
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• 2007

Predicting the noise radiated from vibrating structures is important in the automotive, aerospace, construction equipment, and defense industries. In this paper, a numerical implementation of the boundary element method in solving the Helmholtz integral equation for radiated noise prediction is presented. To predict the noise emitted by vibrating structure, the developed code can use the results from a structure analysis performed by a multi-purpose structural finite element code like ANSYS and directly measured data by non-contact vibration sensor like Laser Doppler Vibrometer. To verify the accuracy of developed code, two kinds of verification are perfomed. Firstly, the computer code used the harmonic analysis results of ANSYS in simple model and try to match with SYSNOISE. After matching with simulation results, the code compared with the result from SYSNOISE which used the velocity data from the LDV measurement with different number of points. The performance of the developed code for vibro-acoustic noise prediction is presented using the experimental results of the non-contact sensor

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.359-374
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• 2024

A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs). The MARS-LMR code, system transient safety analysis code, was applied to analyze the DBEs. The results of the MARS-LMR code were used as boundary condition for a 3D computational fluid dynamics (CFD) analysis. The peak temperatures considering HCFs satisfied the cladding temperature limit. The temperature and pressure distributions were calculated by ANSYS CFX code, and applied to structural analysis. Structural analysis was performed using ANSYS Mechanical code. The seismic reactivity insertion SSE accident among DBEs had the highest peak cladding temperature and the maximum stress, as the value of 87 MPa. The fuel cladding had over 40 % safety margin, and the strain was below the strain limit. Deformation behavior was elucidated for providing relative coordinate data on each active fuel rod center. Bending deformation resulted in a flower shape, and bowing bundle did not interact with the duct of fuel assemblies. Fuel rod maximum expansion was generated with highest stress. Therefore, it was concluded that the fuel rod cladding of the PGSFR has sufficient structural safety margin during DBEs.

• 한국산업경영시스템학회:학술대회논문집
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• 한국산업경영시스템학회 2002년도 춘계학술대회
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• pp.445-454
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• 2002

This article explains the theory of multiple mode/physical coordinate synthesis method in order to analyze the dynamic characteristics for an huge marine engine. The theory leads to make a simulation code. The natural frequencies obtained from the simulation code is compared to those from a commercial analysis software, ANSYS. The simulation code is well reviewed.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집B
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• pp.651-657
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• 2001

This article explains the theory of multiple mode/physical coordinate synthesis method in order to analyze the dynamic characteristics for an huge marine engine. The theory leads to make a simulation code. The natural frequencies obtained from the simulation code is compared to those from a commercial analysis software, ANSYS. The simulation code is well reviewed.

• 대한기계학회논문집A
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• 제24권3호
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• pp.645-652
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• 2000

A method for shape design sensitivity analysis is proposed utilizing commercial software ANSYS for thermal conduction problems. While the sensitivity formula is derived analytically by introduing adjoint variable concept, sensitivity calculation in practice as well as the primal and adjoint solution of thermal conduction is performed using the ANSYS very easily. Since the formula always takes boundary integral form, sensitivity evaluation in ANSYS requires a little more addition of post-processing routine which involves evaluation of boundary variable from the obtained solution. Though the BEM has been used as a better tool for this purpose, the present study shows it can also be calculated using any kind of analysis code such as ANSYS since the formula is based on analytic nature. Therefore the present study provides a new and efficient way of optimization which was not possible before using commercial software. The usefulness of the method is illustrated via a weight minimization problem of thermal diffuser.

• 시스템엔지니어링학술지
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• 제13권1호
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• pp.33-39
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• 2017

This paper describes the system engineering approach for the heat transfer analysis of plus7 fuel rod for APR1400 using, a commercial software, ANSYS. The fuel rod is composed of fuel pellets, fill gas, end caps, plenum spring and cladding. The heat is transferred from the pellet outward by conduction through the pellet, fill gas and cladding and further by convection from the cladding surface to the coolant in the flow channel. The goal of this paper is to demonstrate the temperature and heat flux change from the fuel centerline to the cladding surface when having maximum fuel centerline temperature at 100% power. This phenomenon is modelled using the ANSYS FEM code and analyzed for steady state temperature distribution across the fuel pellet and clad and the results were compared to the standard values given in APR1400 SSAR. Specifically the applicability of commercial software in the evaluation of nuclear fuel temperature distribution has been accounted. It is note that special codes have been used for fuel rod mechanical analysis which calculates interrelated effects of temperature, pressure, cladding elastic and plastic behavior, fission gas release, and fuel densification and swelling under the time-varying irradiation conditions. To satisfactorily meet this objective we apply system engineering methodologies to formulate the process and allow for verification and validation of the results acquired. The close proximity of the results obtained validated the accuracy of the FEM analysis of the 2D axisymmetric model and 3D model. This result demonstrated the validity of commercial software instead of proprietary in-house code that is more costly to develop and maintain.