Evaluation of algorithms for the solution of the drift flux equations on advanced computers
Creators
- 1. North Carolina State Univ., Raleigh, NC (USA). Dept. of Nuclear Engineering
Description
Current efforts are underway to develop and evaluate numerical algorithms for the parallel solution of the large sparse matrix equations associated with the finite difference representation of the macroscopic Navier-Stokes equations. Our work has concentrated on the one-dimensional drift flux form of the Navier-Stokes equations. Direct and iterative algorithms that may be suitable for implementation on parallel computer architectures are evaluated in terms of accuracy and overall execution speed. This work has application to engineering and training simulators, on-line process control systems, and engineering work stations where increased computational speeds are required. Results from a drift flux code run on a large supercomputer indicate that faster than real time simulations are possible with several of the algorithms being considered, however, the direct algorithms have provided the fastest and most accurate results
Additional details
Additional titles
- Augmented title (English)
- FLOC code
Publishing Information
- ISBN
- 0-919784-11-9
- Imprint Title
- Proceedings of the 2. international conference on simulation methods in nuclear engineering
- Imprint Pagination
- 950 p.
- Journal Page Range
- p. 678-699.
- Report number
- INIS-mf--12868(v.1,2)
Conference
- Title
- 2. International conference on simulation methods in nuclear engineering.
- Dates
- 14-16 Oct 1986.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 22064296
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; F CODES; HEAT TRANSFER; MC GUIRE-1 REACTOR; NAVIER-STOKES EQUATIONS; NUMERICAL SOLUTION; PARALLEL PROCESSING; SUPERCOMPUTERS; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; COMPUTERS; DIFFERENTIAL EQUATIONS; DIGITAL COMPUTERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID FLOW; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; PROGRAMMING; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS