Algorithms for the solution of the mixture drift-flux equations on multi-CPU vector pipeline machines
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7180793
Current codes used for best-estimate reactor thermal-hydraulic analysis such as transient reactor analysis code (TRAC) and RELAP require long run times on large mainframe computers. The run times have been reduced using vectorized versions on supercomputers and parallelized versions on multi-CPU machines. However, these efforts have dealt with modifying the present algorithms to run on the new architectures rather than developing new specialized algorithms. In particular, the numerical solution of equations governing heat transfer and fluid flow in reactor systems involves the solution of large sparse matrix equations. The work being presented here involves the development and evaluation of algorithms to solve these large sparse matrix equations on parallel and vector machines. The objective of this work is to solve the matrix equations rapidly enough so that the reactor system simulation will run in real, or better than real time. With this real-time simulation ability using state-of-the-art thermal-hydraulics codes the models used in training simulators could be upgraded, complex reactor system design and analysis could be performed interactively on engineering workstations, and the run times required for licensing calculations could be significantly reduced. A three-equation drift-flux code named FLOC was written for use in evaluating algorithm performance.
- Research Organization:
- North Carolina State Univ., Raleigh
- OSTI ID:
- 7180793
- Report Number(s):
- CONF-861102-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 53
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALGORITHMS
ANALOG SYSTEMS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
DESIGN
ENERGY TRANSFER
ENGINEERING
F CODES
FLUID MECHANICS
FUNCTIONAL MODELS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL LOGIC
MECHANICS
PARALLEL PROCESSING
PROGRAMMING
PWR TYPE REACTORS
REACTOR SIMULATORS
REACTORS
SIMULATION
SIMULATORS
VECTOR PROCESSING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALGORITHMS
ANALOG SYSTEMS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
DESIGN
ENERGY TRANSFER
ENGINEERING
F CODES
FLUID MECHANICS
FUNCTIONAL MODELS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL LOGIC
MECHANICS
PARALLEL PROCESSING
PROGRAMMING
PWR TYPE REACTORS
REACTOR SIMULATORS
REACTORS
SIMULATION
SIMULATORS
VECTOR PROCESSING
WATER COOLED REACTORS
WATER MODERATED REACTORS