Published July 2007
| Version v1
Journal article
Reactor power control hardware-in-the-loop simulation in nuclear power station base on the internet remote control
Creators
- 1. School of Nuclear Science and Technology, Nanhua Univ., Hengyang (China)
- 2. China Inst. of Atomic Energy, Beijing (China)
Description
In this paper, an emulator of hardware-in-the-loop was developed using the VC++ 6.0 and Matlab. The mathematical model of PWR reactor core for the simulation of the power control system of PWR nuclear power station was used. The simulation is constitute of control feedback unit and response on the spot. The changes of reactor power, reactivity and the action of the control rods in the core were simulated on line. The control signal is transmitted between the microcomputer and the industrial computer by the internet network. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Electronics and Detection Technology
- Journal Volume
- 27
- Journal Issue
- 4
- Journal Page Range
- p. 643-646
- ISSN
- 0258-0934
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 41053376
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTROL ROD DRIVES; CONTROL SYSTEMS; DATA TRANSMISSION; FEEDBACK; INTERNET; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; ON-LINE SYSTEMS; POWER DENSITY; PWR TYPE REACTORS; REACTIVITY; REACTOR CORES; REACTOR SIMULATORS; REMOTE CONTROL; RESPONSE FUNCTIONS
- Descriptors DEC
- ANALOG SYSTEMS; COMMUNICATIONS; COMPUTER NETWORKS; CONTROL; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; FUNCTIONS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; SIMULATORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs., 5 refs.