Development of a high order and multi-dimensional nodal code, ACNEC3D, for reactor core analysis

Annals of Nuclear Energy

Volumn 55, Issue , 2013, Pages 211-224

  Poursalehi, N ^a   Zolfaghari, A ^a   Minuchehr, A ^a  

^a SHAHID BEHESHTI UNIVERSITY   (Iran)

Author keywords

Average current nodal expansion method; Diffusion equation; First and second orders of solution; Zeroth

Indexed keywords

AVERAGE CURRENTS; BALANCE EQUATIONS; COARSE MESHES; COMPUTATIONAL COSTS; CORE CALCULATIONS; CPU MEMORY; DIFFUSION EQUATIONS; ERROR REDUCTION; FLUX GRADIENTS; HIGH FLUX; HIGHER EFFICIENCY; ITERATIVE SOLUTIONS; MESH SIZE; MULTI-GROUP; NODAL EXPANSION METHOD; NODAL METHOD; RECTANGULAR GEOMETRY; REFERENCE SOLUTION; SECOND ORDERS; SECOND-ORDER SOLUTIONS; ZEROTH;

ERRORS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR CORES; THERMAL EXPANSION;

ITERATIVE METHODS;

EID: 84872712613     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2012.10.022     Document Type: Article

References (24)

1. R.T. Ackroyd Finite Element Methods for Particle Transport Applications to Reactor and Radiation Physics 1997 Research Studies Press Ltd. England
2. N.Z. Cho, Y.H. Kim, and K.W. Park Extension of analytic function expansion nodal method to multigroup problems in hexagonal-Z geometry Nucl. Sci. Eng. 126 1997 35
3. Cho, N.Z., Lee, J., Kim, D.S., Yang, C.Y., Jo, J.C., 2005. Improved Features and Verification of an AFEN Method Code in Hexagonal-Z 3-D Geometry for Neutron Diffusion Calculation submitted to American Nuclear Society Annual Meeting, San Diego, CA.
4. Finnemann, H., 1975. A Consistent nodal method for the analysis of space-time effects in large LWRs. In: Proceedings of the Joint NEACRP/CSNI Specialists Meeting on New Developments in Three-Dimensional Neutron Kinetics and Review of Kinetics Benchmark Calculations. MRR 145, January 22-24, Munich, p. 131.
5. H. Finnemann, F. Bennewitz, and M.R. Wagner Interface current techniques for multidimensional reactor calculations Atomkernenergie 30 1977 123 128 (Pubitemid 8560008)
6. H.D. Fischer, and H. Finnemann The nodal integration method-a diverse solver for neutron diffusion problems Atomkernenergie 39 1981 229
7. Fowler, T.B., 1999. CITATION-LDI2 Nuclear Reactor Core Analysis Code System. CCC-643, Oak Ridge National Laboratory, Oak Ridge, Tennessee.
8. S. Han, S. Dulla, and P. Ravetto Computational Methods for Multidimensional Neutron Diffusion Problems. Science and Technology of Nuclear Installations 2009 Hindawi Publishing Corporation (ID 973605)
9. Langenbuch, S., Murer, W., Werner, W., 1975. Simulation of Transient with Space-Dependent Feedback by Coarse Mesh Flux Expansion Method. NEACRP/CSNI Specialists. Meeting MRR 145, Garching, p. 173.
10. S. Langenbuch, W. Murer, and W. Werner Coarse-mesh flux expansion method for the analysis of space-time effects in large light water reactor cores Nucl. Sci. Eng. 63 1977 437 456
11. S. Langenbuch, W. Murer, and W. Werner High-order schemes for neutron kinetics calculations, based on a local polynomial approximation Nucl. Sci. Eng. 64 1977 508 516 (Pubitemid 8550038)
12. Lawrence, R.D., 1979. A nodal Green's Function Method for Multidimensional Neutron Diffusion Calculations. Thesis, Nuclear Engineering Program, Univ. of Illinois, Urbana.
13. R.D. Lawrence Progress in nodal methods for the solution of the neutron diffusion and transport equations Prog. Nucl. Energy 17 3 1986 271 301 (Pubitemid 17461382)
14. J. Lee, and N.Z. Cho AFEN method and its solutions of the hexagonal three-dimensional VVER-1000 benchmark problem Prog. Nucl. Energy 48 2006 880 890 (Pubitemid 44779801)
15. Micheelson, B., Nelturp, H., 1973. The 3-D IAEA Benchmark Problem. RISO-M-1572.
16. J.M. Noh, and N.Z. Cho A new diffusion nodal method based on analytic basis function expansion Trans. Am. Nucl. Soc. 69 1993 462 463
17. J.M. Noh, and N.Z. Cho A new approach of analytic basis function expansion to neutron diffusion calculation Nucl. Sci. Eng. 116 1994 165
18. M. Pimenta de abreu, F. Carvalho da silva, and A. Carlos marques alvim Transverse net leakage into the second order Nodal Expansion Method Ann. Nucl. Energy 22 2 1995 85 95
19. Putney, J.M., 1984. Nodal Methods for Solving the Diffusion Equation for Fast Reactor Analysis. Ph.D. Thesis, University of London.
20. Shober, R.A., 1978. A Nodal Method for Solving Transient Few-Group Neutron Diffusion Equations. ANL-78-51, Argonne National Laboratory.
21. Smith, K.S., 1979. An Analytic Nodal Method for Solving the Two-Group, Multidimensional, Static and Transient Neutron Diffusion Equations. Submitted in Partial Fulfillment of The Requirements for The Degrees of Nuclear Engineer and Master of Science at The Massachusetts Institute of Technology.
22. P.J. Turinsky Few Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady State and Transient Problems 1994 Electric Power Research Center, North Carolina State University
23. M.R. Wagner, K.H. Finnemann, K. Koebke, and J. Winter Validation of the nodal expansion method and the depletion program MEDIUM-2 by Bechmark calculations and direct comparisons with experiments Atomkernenergie 30 1977 129 135 (Pubitemid 8560009)
24. S.W. Woo, N.Z. Cho, and J.M. Noh The analytic function expansion nodal method refined with transverse gradient basis functions and interface flux moments Nucl. Sci. Eng. 139 2001 156