Validity of single-cycle objective functions for multicycle reload design optimization
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7129679
- North Carolina State Univ., Raleigh, NC (United States)
Beyond the equilibrium cycle scoping calculations used for determining numbers of feed assemblies and enrichment estimates, multicycle reload design currently consists of stagewise optimization of single-cycle core loading patterns, typically extending over a short-term planning horizon of perhaps three reload cycles. Particularly in transition cycles, however, optimizing a loading pattern over a single cycle for a stated objective, such as minimum core leakage, may have an adverse impact on subsequent cycles. The penalties paid may be in the form of reduced thermal margin or an increase in feed enrichment due to insufficient reactivity carryover from the [open quotes]optimized[close quotes] cycle. In view of current practices, a study was performed that examined the behavior of the loading pattern as a function of the objective functions selected as implemented in the stagewise optimization of single-cycle core loading patterns from initial transition cycle through equilibrium using the FORMOSA-P code. The objective functions studied were region average discharge burnup maximization (with enrichment search) and feed enrichment minimization. It is noted at the beginning that the maximization of region average discharge has no meaning for the equilibrium cycle because region average discharge burnup is explicitly set by the feed size and cycle length independent of the loading pattern. In the nonequilibrium cycle, however, it was reasoned that this objective would provide the maximum reactivity carryover throughout the transition and thus have a direct effect on minimizing the multicycle levelized fuel cost.
- OSTI ID:
- 7129679
- Report Number(s):
- CONF-931160--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
BURNUP
COMPUTER CODES
ENRICHED URANIUM REACTORS
ENRICHMENT
F CODES
FUEL ASSEMBLIES
FUEL MANAGEMENT
OPTIMIZATION
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR FUELING
REACTOR PHYSICS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
BURNUP
COMPUTER CODES
ENRICHED URANIUM REACTORS
ENRICHMENT
F CODES
FUEL ASSEMBLIES
FUEL MANAGEMENT
OPTIMIZATION
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR FUELING
REACTOR PHYSICS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS