Vectorization of transport and diffusion computations on the CDC Cyber 205
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6078064
The development and testing of alternative numerical methods and computational algorithms specifically designed for the vectorization of transport and diffusion computations on a Control Data Corporation (CDC) Cyber 205 vector computer are described. Two solution methods for the discrete ordinates approximation to the transport equation are summarized and compared. Factors of 4 to 7 reduction in run times for certain large transport problems were achieved on a Cyber 205 as compared with run times on a CDC-7600. The solution of tridiagonal systems of linear equations, central to several efficient numerical methods for multidimensional diffusion computations and essential for fluid flow and other physics and engineering problems, is also dealt with. Among the methods tested, a combined odd-even cyclic reduction and modified Cholesky factorization algorithm for solving linear symmetric positive definite tridiagonal systems is found to be the most effective for these systems on a Cyber 205. For large tridiagonal systems, computation with this algorithm is an order of magnitude faster on a Cyber 205 than computation with the best algorithm for tridiagonal systems on a CDC-7600.
- Research Organization:
- Bettis Atomic Power Laboratory, P.O. Box 79, West Mifflin, PA 15122-0079
- DOE Contract Number:
- AC11-76PN00014
- OSTI ID:
- 6078064
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 92:1; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
CDC COMPUTERS
COMPUTER CALCULATIONS
COMPUTERS
DIFFERENTIAL EQUATIONS
DIGITAL COMPUTERS
DISCRETE ORDINATE METHOD
EQUATIONS
FACTORIZATION
FLUID FLOW
ITERATIVE METHODS
MATHEMATICAL LOGIC
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
PERFORMANCE
PROGRAMMING
SUPERCOMPUTERS
TRANSPORT THEORY
USES
VECTOR PROCESSING
220100* -- Nuclear Reactor Technology-- Theory & Calculation
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
CDC COMPUTERS
COMPUTER CALCULATIONS
COMPUTERS
DIFFERENTIAL EQUATIONS
DIGITAL COMPUTERS
DISCRETE ORDINATE METHOD
EQUATIONS
FACTORIZATION
FLUID FLOW
ITERATIVE METHODS
MATHEMATICAL LOGIC
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
PERFORMANCE
PROGRAMMING
SUPERCOMPUTERS
TRANSPORT THEORY
USES
VECTOR PROCESSING