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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 43 - 54 (12page)
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In the present paper, development of the three-dimensional (3D) computational code basedon Galerkin finite element method (GFEM) for solving the multigroup forward/adjointdiffusion equation in both rectangular and hexagonal geometries is reported. Linearapproximation of shape functions in the GFEM with unstructured tetrahedron elements isused in the calculation. Both criticality and fixed source calculations may be performedusing the developed GFEM-3D computational code. An acceptable level of accuracy at a lowcomputational cost is the main advantage of applying the unstructured tetrahedron elements.
The unstructured tetrahedron elements generated with Gambit software are usedin the GFEM-3D computational code through a developed interface. The forward/adjointmultiplication factor, forward/adjoint flux distribution, and power distribution in thereactor core are calculated using the power iteration method. Criticality calculations arebenchmarked against the valid solution of the neutron diffusion equation for InternationalAtomic Energy Agency (IAEA)-3D and Water-Water Energetic Reactor (VVER)-1000 reactorcores. In addition, validation of the calculations against the P1 approximation of thetransport theory is investigated in relation to the liquid metal fast breeder reactorbenchmark problem. The neutron fixed source calculations are benchmarked through acomparison with the results obtained from similar computational codes. Finally, ananalysis of the sensitivity of calculations to the number of elements is performed.
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참고문헌 (24)
참고문헌 신청
L.F. Richardson / 1911 / The approximate arithmetical solution by finite differences of physical problems involving differential equations, with an application to the stresses in a masonry dam / Philos. Trans. R. Soc. Lon. A 210:307~357
K. Ivanov / 1994 / An effective solution scheme of a three-dimensional reactor core model in hexagonal geometry / Comput. Phys. Commun 82:1~16
V.G. Zimin / 2002 / Polynomial nodal method for solving neutron diffusion equations in hexagonal-z geometry / Ann. Nucl. Energy 29:1105~1117
A. Hebert / 1987 / Development of the nodal collocation method for solving the neutron diffusion equation / Ann. Nucl. Energy 14:527~541
K.S. Smith / 1979 / An Analytic Nodal Method for Solving the Two-Group, Multidimensional, Static and Transient Neutron Diffusion Equations / Massachusetts Institute of Technology
K. Ivanov / 1994 / An effective solution scheme of a three-dimensional reactor core model in hexagonal geometry / Comput. Phys. Commun 82:1~16
V.G. Zimin / 2002 / Polynomial nodal method for solving neutron diffusion equations in hexagonal-z geometry / Ann. Nucl. Energy 29:1105~1117
A. Hebert / 1987 / Development of the nodal collocation method for solving the neutron diffusion equation / Ann. Nucl. Energy 14:527~541
K.S. Smith / 1979 / An Analytic Nodal Method for Solving the Two-Group, Multidimensional, Static and Transient Neutron Diffusion Equations / Massachusetts Institute of Technology
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