Published October 2001 | Version v1
Miscellaneous

A nuclear reactor power controller using a receding horizon control method

  • 1. Chosun Univ., Kwangju (Korea, Republic of)

Description

A receding horizon control method is applied to design a fully automatic controller for thermal power in a reactor core. The basic concept of the receding horizon control is to solve an optimization problem for a finite future at current time and to implement as the current control input the first optimal control input among the solutions of the finite time steps. The procedure is then repeated at each subsequent instant. The receding horizon controller is designed so that the difference between the output and the desired output is minimized and the variation of the control rod position is small. The nonlinear PWR plant model (nonlinear point kinetics equation with six delayed neutron groups and the lumped thermal-hydraulic balance equations) was used to verify the proposed controller of reactor power. And a controller design model used for designing the receding horizon controller was obtained by applying a parameter estimation algorithm. From numerical simulation results, the performances of this controller for the 5%/min ramp increase or decrease of a desired load and its 10% step increase or decrease which are design requirements are proved to be excellent

Part of:
Proceedings of the Korean Nuclear Society autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society autumn meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[12 p.]

Conference

Title
2001 autumn meeting of the Korean Nuclear Society
Dates
24-26 Oct 2001
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33065410
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONTROL ELEMENTS; DESIGN; PERFORMANCE; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR CORES; REACTOR KINETICS EQUATIONS; SIMULATION
Descriptors DEC
CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; EQUATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
19 refs, 7 figs, 1 tab