Discrete ordinates nodal method for one-dimensional neutron transport calculation in curvilinear geometries

Nuclear Science and Engineering

Volumn 133, Issue 3, 1999, Pages 350-357

  Wu, Yican ^a   Xie, Zhongsheng ^b   Fischer, Ulrich ^c  

^a INSTITUTE OF PLASMA PHYSICS   (China)

^b XI'AN JIAOTONG UNIVERSITY   (China)

^c KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

APPROXIMATION THEORY; GREEN'S FUNCTION; NEUTRONS; NUCLEAR PHYSICS; POLYNOMIALS;

DISCRETE ORDINATE NODAL METHOD; LEGENDRE POLYNOMIALS; NEUTRON TRANSPORT EQUATIONS; SPATIAL DIAMOND DIFFERENCING METHOD;

NUCLEAR REACTORS;

EID: 0033221763     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE99-A2095     Document Type: Article

References (14)

1. J. J. DUDERSTADT and W. R. MARTIN, Transport Theory, Wiley Interscience, New York (1979).
2. H. GREENSPAN, C. N. KELBER, and D. OKRENT, Computing Method in Reactor Physics, pp. 171-226, Gordon and Breach Science Publishers (1968).
3. W. W. ENGLE, "A User's Manual for ANISN," USAEC Report K-1693, U.S. Atomic Energy Commission (1967); see also "ANISN-ORNL, A One-Dimensional Discrete Ordinates Transport Code," CCC-254, Oak Ridge National Laboratory (1973).
4. W. W. ENGLE, "A User's Manual for ANISN," USAEC Report K-1693, U.S. Atomic Energy Commission (1967); see also "ANISN-ORNL, A One-Dimensional Discrete Ordinates Transport Code," CCC-254, Oak Ridge National Laboratory (1973).
5. R. D. LAWRENCE and J. J. DORNING, "New Coarse-Mesh Diffusion and Transport Theory Methods for the Efficient Numerical Calculation of Multi-Dimensional Reactor Power Distributions," Proc. Conf. Calculation of 3-Dimensional Rating Distribution in Operating Reactors, Paris, France (1970).
6. R. E. PEVEY, "Development of a New Two-Dimensional Cartesian Geometry Nodal Multigroup Discrete Ordinates Method," ORNL/CSD/TM-182, U.S. Atomic Energy Commission (1982).
7. R. D. LAWRENCE and J. J. DORNING, "A Discrete Nodal Integral Transport Theory for Multidimensional Reactor Physics and Shielding Calculations," Proc. Topl. Mtg. Advances in Reactor Physics and Shielding, Sun Valley, Idaho, September 14-17, 1980, American Nuclear Society (1980).
8. M. R. WAGNER, "A Nodal Discrete-Ordinate Method for the Numerical Solution of the Multidimensional Transport Equation," Proc. American Nuclear Engineering, Vol. 2, p. 4-117, Williamsburg, Virginia, 1979.
9. W. F. WALTERS and R. D. O'DELL, "Nodal Methods for Discrete Ordinates Transport Problems in (X,Y) Geometry," Proc. Int. Topl. Mtg. Advances in Mathematical Methods for the Solution of Nuclear Engineering Problems, Vol. 1, p. 115, Munich, Germany, 1981.
10. E. W. LARSEN and J. E. MOREL, "Asymptotic Solutions of Numerical Transport Problems in Optically Thick, Diffusive Regimes II," J. Comput. Phys., 83, 212 (1989).
11. B. MINOR and K. MATHEWS, "Exponential Characteristic Spatial Quadrature for Discrete Ordinates Radiation Transport with Rectangular Cells," Nucl. Sci. Eng., 120, 165 (1995).
12. M. L. ADAMS and W. R. MARTIN, "Diffusion Synthetic Acceleration of Discontinuous Finite Element Transport Iterations," Nucl. Sci. Eng., 111, 145 (1992).
13. J. WOOD and M. R. WILLIAMS, "Recent Progress in the Application of the Finite Element Method to the Neutron Transport Equation," Prog. Nucl. Energy, 14, 29 (1984).
14. J. WOOD, "A Multigroup Finite-Element Solution of the Neutron Transport Equation - II, R-Z Geometry," Ann. Nucl. Energy, 12, 221 (1985).