Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

FORMOSA-P multiple adaptive penalty function methodology

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:426519
;  [1]
  1. North Carolina State Univ., Raleigh, NC (United States)
The nuclear fuel management optimization code FORMOSA-P has been developed to determine the family of near-optimum loading patterns for pressurized water reactors. The FORMOSA-P code utilizes the nonlinear stochastic optimization approach of simulated annealing, wherein an objective function is calculated to evaluate the suitability of the candidate loading patterns. During the course of a simulated annealing cooling cycle, the penalty function multiplier is adaptively increased to eliminate the penalty constraint violations by the end of the cooling cycle. In early versions of FORMOSA-P, only one adaptive penalty function, for power peaking, was available. All other design constraints were handled via true-false constraints. The introduction of generalized perturbation theory (GPT) error control which greatly increased the design space accessible in a single cooling cycle, and modern core designs, which are increasingly tightly constrained by multiple design constraints, however, have made these true-false constraints undesirable; thus, a methodology for inclusion of multiple adaptive penalty constraints has now been developed.
OSTI ID:
426519
Report Number(s):
CONF-961103--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English

Similar Records

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 00:00:00 EDT 1995 · Nuclear Science and Engineering · OSTI ID:131674

Evaluation of reactivity shutdown margin for nuclear fuel reload optimization
Journal Article · Sat Dec 30 23:00:00 EST 1995 · Transactions of the American Nuclear Society · OSTI ID:411795

Integration of the FORMOSA PWR in-core fuel management optimization code into nuclear design code systems
Conference · Mon Dec 31 23:00:00 EST 1990 · Transactions of the American Nuclear Society; (United States) · OSTI ID:5981882