Integration of the FORMOSA PWR in-core fuel management optimization code into nuclear design code systems
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5981882
- North Carolina State Univ., Raleigh (United States)
- Carolina Power and Light Co., Raleigh, NC (United States)
North Carolina State University has, in collaboration with Duke Power and Carolina Power and Light Company (CP and L), developed an in-core fuel management code, FORMOSA, which automatically provides the much needed computational capability to determine optimal pressurized water reactor loading patterns (LPs) for a variety of objective functions. FORMOSA employs simulated annealing to control the optimization process, using the exchange of fuel assemblies between randomly selected locations to seek improvements in the LP. Candidate patterns are assessed using second-order generalized perturbation theory (GPT) expressions for the characteristics of interest based on a two-dimensional, coarse-mesh finite difference discretization of the two-group neutron diffusion equations. Before its potential can be exploited, FORMOSA must be integrated into a utility's nuclear design system. This task was undertaken at both Duke Power and CP and L, which employ the Studsvik and Scandpower methodologies, respectively.
- OSTI ID:
- 5981882
- Report Number(s):
- CONF-910603--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALGORITHMS
CATAWBA-1 REACTOR
COMPUTER CODES
DESIGN
ENRICHED URANIUM REACTORS
F CODES
FINITE DIFFERENCE METHOD
FUEL MANAGEMENT
ITERATIVE METHODS
MATHEMATICAL LOGIC
MESH GENERATION
MULTIPLICATION FACTORS
NUMERICAL SOLUTION
OPTIMIZATION
PERTURBATION THEORY
PHYSICS
POWER DENSITY
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR FUELING
REACTOR LATTICES
REACTOR PHYSICS
REACTORS
S CODES
THERMAL REACTORS
TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALGORITHMS
CATAWBA-1 REACTOR
COMPUTER CODES
DESIGN
ENRICHED URANIUM REACTORS
F CODES
FINITE DIFFERENCE METHOD
FUEL MANAGEMENT
ITERATIVE METHODS
MATHEMATICAL LOGIC
MESH GENERATION
MULTIPLICATION FACTORS
NUMERICAL SOLUTION
OPTIMIZATION
PERTURBATION THEORY
PHYSICS
POWER DENSITY
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR FUELING
REACTOR LATTICES
REACTOR PHYSICS
REACTORS
S CODES
THERMAL REACTORS
TWO-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS