Integration of the FORMOSA PWR in-core fuel management optimization code into nuclear design code systems

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5981882

Sawyer, J M; Murphy, P R; Parks, G T; Maldonado, G I; Turinsky, P J ^[1]; Daniels, D A ^[2]

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1. North Carolina State Univ., Raleigh (United States)
2. 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-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: Annual meeting of the American Nuclear Society (ANS), Orlando, FL (United States), 2-6 Jun 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL MANAGEMENT
F CODES
PWR TYPE REACTORS
ALGORITHMS
CATAWBA-1 REACTOR
DESIGN
FINITE DIFFERENCE METHOD
MESH GENERATION
MULTIPLICATION FACTORS
OPTIMIZATION
PERTURBATION THEORY
POWER DENSITY
REACTOR CORES
REACTOR FUELING
REACTOR LATTICES
REACTOR PHYSICS
S CODES
TWO-DIMENSIONAL CALCULATIONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
ITERATIVE METHODS
MATHEMATICAL LOGIC
NUMERICAL SOLUTION
PHYSICS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled