Development of a polynomial nodal method with flux and current discontinuity factors

Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992.

[1]  Allan F. Henry,et al.  Nuclear Reactor Analysis , 1977, IEEE Transactions on Nuclear Science.

[2]  G. P. Bottoni,et al.  Neutronic aspects of the LWR core simulator CETRA , 1979 .

[3]  T. M. Sutton Wielandt iteration as applied to the nodal expansion method , 1988 .

[4]  K. Smith,et al.  ASSEMBLY HOMOGENIZATION TECHNIQUES FOR LIGHT WATER REACTOR ANALYSIS , 1986 .

[5]  B W BARTLETT Nuclear science and engineering school curricula. , 1951, Nucleonics.

[6]  B. Stehle D3D. Ein FORTRAN-Programm zur Loesung der stationaeren dreidimensionalen Multigruppendiffusionsgleichungen , 1975 .

[7]  Jack J. Dongarra,et al.  Performance of various computers using standard linear equations software in a FORTRAN environment , 1988, CARN.

[8]  J. Duderstadt,et al.  Nuclear reactor analysis , 1976 .

[9]  K. R. Rempe,et al.  Testing and applications of the QPANDA nodal model , 1988 .

[10]  R. A. Shober A Nodal Method for Solving Transient Fewgroup Neutron Diffusion Equations , 1978 .

[11]  R. D. Lawrence PROGRESS IN NODAL METHODS FOR THE SOLUTION OF THE NEUTRON DIFFUSION AND TRANSPORT EQUATIONS , 1986 .

[12]  J. M. Aragones,et al.  A Linear Discontinuous Finite Difference Formulation for Synthetic Coarse-Mesh Few-Group Diffusion Calculations , 1986 .

[13]  Kord Sterling Smith,et al.  Spatial homogenization methods for light water reactor analysis , 1980 .

[14]  D. R. Vondy,et al.  VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport, version II. [LMFBR] , 1975 .

[15]  G. Buckel,et al.  Benchmark Calculations for a Sodium-Cooled Breeder Reactor by Two- and Three-Dimensional Diffusion Methods—II , 1977 .

[16]  Myung Hyun Kim The use of bilinearly weighted cross sections for few-group transient analysis , 1988 .

[17]  Kord Smith,et al.  An analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equations , 1979 .