Parallel solutions of the two-group neutron diffusion equations
Recent efforts to adapt various numerical solution algorithms to parallel computer architectures have addressed the possibility of substantially reducing the running time of few-group neutron diffusion calculations. The authors have developed an efficient iterative parallel algorithm and an associated computer code for the rapid solution of the finite difference method representation of the two-group neutron diffusion equations on the CRAY X/MP-48 supercomputer having multi-CPUs and vector pipelines. For realistic simulation of light water reactor cores, the code employees a macroscopic depletion model with trace capability for selected fission product transients and critical boron. In addition to this, moderator and fuel temperature feedback models are also incorporated into the code. The validity of the physics models used in the code were benchmarked against qualified codes and proved accurate. This work is an extension of previous work in that various feedback effects are accounted for in the system; the entire code is structured to accommodate extensive vectorization; and an additional parallelism by multitasking is achieved not only for the solution of the matrix equations associated with the inner iterations but also for the other segments of the code, e.g., outer iterations.
- OSTI ID:
- 6919002
- Report Number(s):
- CONF-8711195-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 55; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
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73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALGORITHMS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
COMPUTERS
CRAY COMPUTERS
DIFFERENTIAL EQUATIONS
EQUATIONS
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MATHEMATICAL LOGIC
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NEUTRON DIFFUSION EQUATION
NUMERICAL SOLUTION
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WATER COOLED REACTORS
WATER MODERATED REACTORS