• Interaction and multiscale mechanics
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• v.6 no.2
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• pp.197-210
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• 2013

A fundamental trend of processor architecture evolving towards exaflops is fast increasing floating point performance (so-called "free" flops) accompanied by much slowly increasing memory and network bandwidth. In order to fully enjoy the "free" flops, a numerical algorithm of PDEs should request more flops per byte or increase arithmetic intensity. A meshfree/GFEM approximation can be the class of the algorithm. It is shown in a GFEM without extra dof that the kind of approximation takes advantages of the high performance of manycore GPUs by a high accuracy of approximation; the "expensive" method is found to be reversely hardware-efficient on the emerging architecture of manycore.

• Nuclear Engineering and Technology
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• v.48 no.1
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• pp.43-54
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• 2016

In the present paper, development of the three-dimensional (3D) computational code based on Galerkin finite element method (GFEM) for solving the multigroup forward/adjoint diffusion equation in both rectangular and hexagonal geometries is reported. Linear approximation of shape functions in the GFEM with unstructured tetrahedron elements is used in the calculation. Both criticality and fixed source calculations may be performed using the developed GFEM-3D computational code. An acceptable level of accuracy at a low computational cost is the main advantage of applying the unstructured tetrahedron elements. The unstructured tetrahedron elements generated with Gambit software are used in the GFEM-3D computational code through a developed interface. The forward/adjoint multiplication factor, forward/adjoint flux distribution, and power distribution in the reactor core are calculated using the power iteration method. Criticality calculations are benchmarked against the valid solution of the neutron diffusion equation for International Atomic Energy Agency (IAEA)-3D and Water-Water Energetic Reactor (VVER)-1000 reactor cores. In addition, validation of the calculations against the $P_1$ approximation of the transport theory is investigated in relation to the liquid metal fast breeder reactor benchmark problem. The neutron fixed source calculations are benchmarked through a comparison with the results obtained from similar computational codes. Finally, an analysis of the sensitivity of calculations to the number of elements is performed.

• Journal of the KSME
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• v.31 no.1
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• pp.34-42
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• 1991

복잡한 형상의 서지 탱크를 CAEDS의 GEOMOD를 이용하여 내부의 리보까지 포함한 용기를 모델링하였으며, 설계 부피를 검사하고 GEOMOD와 GFEM 사이의 직접 데이터 교환을 통하여 구조 해석에 필요한 유한요소를 만들었다. 유한요소법에 최적화 이론을 적용하여 서지탱크의 두께 변화에 따른 응력의 설계 민감도를 구하였으며, 민감도를 근거로 보강 위치 및 국부적인 용기의 두께를 결정하였다. 유한요소법 프로그램(IFES, GFEM)과 솔리드 모델러(GEOMOD), 그리고 최적화 기법(IFES-Optimization)을 모두 통합하여, 최적 설계를 수행함으로써 반복되는 실험에 의한 시간과 경비를 줄임과 동시에 신뢰성 있는 설계방법 및 방향을 제시하였다.

• Nuclear Engineering and Technology
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• v.51 no.6
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• pp.1479-1486
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• 2019

The purpose of the present study is to develop the 3D static and noise simulator based on Galerkin Finite Element Method (GFEM) using the unstructured hexahedral elements. The 3D, 2G neutron diffusion and noise equations are discretized using the unstructured hexahedral by considering the linear approximation of the shape function in each element. The validation of the static calculation is performed via comparison between calculated results and reported data for the VVER-1000 benchmark problem. A sensitivity analysis of the calculation to the element type (unstructured hexahedral or tetrahedron elements) is done. Finally, the neutron noise calculation is performed for the neutron noise source of type of variable strength using the Green function technique. It is shown that the error reduction in the static calculation is considerable when the unstructured tetrahedron elements are replaced with the hexahedral ones. Since the neutron flux distribution and neutron multiplication factor are appeared in the neutron noise equation, the more accurate calculation of these parameters leads to obtaining the neutron noise distribution with high accuracy. The investigation of the changes of the neutron noise distribution in axial direction of the reactor core shows that the 3D neutron noise analysis is required instead of 2D.

• Computational Structural Engineering
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• v.18 no.4 s.70
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• pp.16-22
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• 2005

• Journal of the korean Society of Automotive Engineers
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• v.12 no.3
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• pp.3-8
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• 1990

본 고에서는 자동차의 냉각장치중, 냉각수를 저장하는 기능을 갖는 surge-tank의 내압에 의한 국부적인 균열 발생 방지 및 용기의 응력환화를 목적으로, 범용 구조해석 프로그램인 CAEDS의 여러 모듈(GEOMOD, GFEM, IFES, OPTISEN)을 이용하여 응력해석을 수행한 후, OPTISEN(최적화 해석 모듈)을 적용하여 용기 두께 및 보강재 위치에 따른 설계민감도를 구하여 최적 두께 및 보강재의 최적 위치를 구하였다.

• 연구논문집
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• s.29
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• pp.69-82
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• 1999

Numerical techniques for the simulations of crack propagation are reviewed. This paper highlights the meshless methods as a potential method for the simulations. thus they are reviewed deeply. Especially the theoretical aspects of meshless methods are discussed. and it is shown that all meshless methods are based on the PUM and unified in GFEM even though they are originated from different sources.