Development of a simulation platform for dynamic simulation and control studies of AP1000 nuclear steam supply system
- 1. Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an City 710049 (China)
- 2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041 (China)
Description
Highlights: • A fast-running simulation platform named NCAP was developed on a personal computer using MATLAB/Simulink. • Three types of typical operations, namely 10% step load change, 5%/min ramp load change and load follow were simulated. • NCAP predictions were compared with those obtained by CENTS for the load regulation transients. - Abstract: This paper presents the development, application and performance assessment of a fast-running NCAP (NSSS Control & Analysis Platform) in MATLAB/Simulink environment. First, a nodal core model, a lumped parameter dynamic steam generator model with moving boundary, a non-equilibrium two-regions-three-volumes pressurizer model, and the relevant pipe and plenum models were proposed based on the fundamental conservation of mass, energy and momentum. Then, these first order nonlinear models and the NSSS control systems were implemented in the Simulink by the predefined library blocks. Based on the developed NCAP, three types of typical operational transients, namely the 10% step load change, the 5%/min ramp load change and the daily load follow were simulated to study the dynamic behavior and control characteristics of the AP1000 NSSS. It has been demonstrated that the dynamic responses of the selected key parameters agree well with the general physical rules. In addition, the comparison of load regulation simulation results obtained by NCAP and CENTS shows a good agreement in terms of the changing trends. With the adoption of modular programming techniques, the NCAP facilitates easy modification and runs quickly, which easily allows the control system designer to test and compare various ideas efficiently
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2015.06.026Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2015.06.026;
- PII
- S0306-4549(15)00340-0;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 85
- Journal Page Range
- p. 704-716
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47019438
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTROL SYSTEMS; NONLINEAR PROBLEMS; PERSONAL COMPUTERS; PRESSURIZERS; PWR TYPE REACTORS; STEAM GENERATORS; STEAM SYSTEMS
- Descriptors DEC
- BOILERS; COMPUTERS; DIGITAL COMPUTERS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MICROCOMPUTERS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.