Optimal control for xenon spatial oscillations in load follow of a nuclear reactor

Journal Article · Sat Jan 01 00:00:00 EST 1983 · Nucl. Sci. Eng.; (United States)

OSTI ID:5565802

Cho, N Z; Grossman, L M

A simple core control model is developed for the control of xenon spatial oscillations in load following operations of a current-design nuclear pressurized water reactor. The model is formulated as a linear-quadratic tracking problem in the context of modern optimal control theory, and the resulting two-point boundary problem is solved directly by the techniques of initial value methods. The system of state equations is composed of the one-group diffusion equation with temperature and xenon feedbacks, the iodine-xenon dynamics equations, and an energy balance relation for the core. Control is via full-length and part-length control rod banks, boron, and coolant inlet temperature. The system equations are linearized around an equilibrium state, which is an eigensolution of the nonlinear static equations with feedback. The nonlinear eigenvalue problem is shown to have a unique positive solution under certain conditions by using the bifurcation theory, the solution being obtained by an iteration based on the use of monotone operators. A modal expansion reduces the linearized equations to a lumped parameter system.

• Research Organization: University of California, Berkeley, Department of Nuclear Engineering, Berkeley, California 94720
• OSTI ID: 5565802
• Journal Information: Nucl. Sci. Eng.; (United States), Vol. 83:1
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR KINETICS EQUATIONS
XENON OSCILLATIONS
BORON
BOUNDARY-VALUE PROBLEMS
CONTROL ELEMENTS
COOLANTS
EIGENFUNCTIONS
ENERGY BALANCE
EQUATIONS OF STATE
EQUILIBRIUM
IODINE
NUCLEAR MODELS
ONE-GROUP THEORY
OPTIMAL CONTROL
QUADRATURES
REACTOR CORE DISRUPTION
TEMPERATURE CONTROL
XENON
ACCIDENTS
CONTROL
ELEMENTS
EQUATIONS
FLUIDS
FUNCTIONS
GASES
HALOGENS
MATHEMATICAL MODELS
NEUTRON TRANSPORT THEORY
NONMETALS
POISONING
RARE GASES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SEMIMETALS
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled