Vectorized and multitasked solution of the few-group neutron diffusion equations
A numerical algorithm with parallelism was used to solve the two-group, multidimensional neutron diffusion equations on computers characterized by shared memory, vector pipeline, and multi-CPU architecture features. Specifically, solutions were obtained on the Cray X/MP-48, the IBM-3090 with vector facilities, and the FPS-164. The material-centered mesh finite difference method approximation and outer-inner iteration method were employed. Parallelism was introduced in the inner iterations using the cyclic line successive overrelaxation iterative method and solving in parallel across lines. The outer iterations were completed using the Chebyshev semi-iterative method that allows parallelism to be introduced in both space and energy groups. For the three-dimensional model, power, soluble boron, and transient fission product feedbacks were included. Concentrating on the pressurized water reactor (PWR), the thermal-hydraulic calculation of moderator density assumed single-phase flow and a closed flow channel, allowing parallelism to be introduced in the solution across the radial plane. Using a pinwise detail, quarter-core model of a typical PWR in cycle 1, for the two-dimensional model without feedback the measured million floating point operations per second (MFLOPS)/vector speedups were 83/11.7. 18/2.2, and 2.4/5.6 on the Cray, IBM, and FPS without multitasking, respectively. Lower performance was observed with a coarser mesh, i.e., shorter vector length, due to vector pipeline start-up. For an 18 x 18 x 30 (x-y-z) three-dimensional model with feedback of the same core, MFLOPS/vector speedups of --61/6.7 and an execution time of 0.8 CPU seconds on the Cray without multitasking were measured. Finally, using two CPUs and the vector pipelines of the Cray, a multitasking efficiency of 81% was noted for the three-dimensional model.
- Research Organization:
- North Carolina State Univ., Raleigh, NC (USA). Dept. of Nuclear Engineering
- OSTI ID:
- 5994638
- Journal Information:
- Nucl. Sci. Eng.; (United States), Vol. 101:3
- Country of Publication:
- United States
- Language:
- English
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COMPUTER ARCHITECTURE
PARALLEL PROCESSING
ALGORITHMS
PWR TYPE REACTORS
NEUTRON TRANSPORT
COMPUTER CALCULATIONS
DIFFUSION
EQUATIONS
FINITE DIFFERENCE METHOD
ITERATIVE METHODS
M CODES
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THREE-DIMENSIONAL CALCULATIONS
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NEUTRAL-PARTICLE TRANSPORT
NUMERICAL SOLUTION
PROGRAMMING
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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