Employing nodal generalized perturbation theory for the minimization of feed enrichment during pressurized water reactor in-core nuclear fuel management optimization

Journal Article · Sun Oct 01 04:00:00 EDT 1995 · Nuclear Science and Engineering

OSTI ID:131674

Maldonado, G I; Turinsky, P J; Kropaczek, D J ^[1]; Parks, G T ^[2]

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1. North Carolina State Univ., Raleigh, NC (United States)
2. Cambridge Univ. (United Kingdom). Engineering Dept.

The computer code FORMOSA-P (Fuel Optimization for Reloads Multiple Objectives by Simulated Annealing--PWR) has been developed to address pressurized water reactor (PWR) in-core nuclear fuel management optimization. Until recently, the optimization objectives available to the user included minimization of relative power peaking throughout the cycle, maximization of the end-of-cycle reactivity, and maximization of region-average discharge burnup. In addition, during an optimization, various core attributes (including the preceding objectives) can be optionally activated as constraints via penalty function or to directly reject sampled loading patterns that violate established design limits. The underlying theoretical framework that enables the accurate and efficient calculation of objective and constraint values within the FORMOSA-P code is its higher order, nodal generalized perturbation theory (GPT) neutronics model. The utility of the FORMOSA-P code has been extended to include a traditionally out-of-core decision variable, namely, the fresh (i.e., feed) reload fuel enrichment. This is accomplished by formulating the feed enrichment as a GPT variable that can be adjusted concurrently with changes in the core loading pattern to enforce a target cycle length. This provides a reload designer with the capability to minimize feed enrichment during an in-core optimization while enforcing all other constraints (e.g., power peaking limit, cycle energy requirement, degree of eight-core power tilt, discharge burnup limit, and moderator temperature coefficient limit).

• OSTI ID: 131674
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 2 Vol. 121; ISSN NSENAO; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS
F CODES
FUEL MANAGEMENT
NEUTRON TRANSPORT
NODAL EXPANSION METHOD
NUCLEAR FUELS
PWR TYPE REACTORS
REACTOR FUELING