DEVELOPMENT OF SOFTWARE FOR THE MICROSIMULATOR FOR THE KO-RI-NUCLEAR-POWER-PLANT UNIT-2

Citation
H. Seok et al., DEVELOPMENT OF SOFTWARE FOR THE MICROSIMULATOR FOR THE KO-RI-NUCLEAR-POWER-PLANT UNIT-2, Nuclear technology, 106(3), 1994, pp. 384-396
Citations number
17
Categorie Soggetti
Nuclear Sciences & Tecnology
Journal title
ISSN journal
00295450
Volume
106
Issue
3
Year of publication
1994
Pages
384 - 396
Database
ISI
SICI code
0029-5450(1994)106:3<384:DOSFTM>2.0.ZU;2-Q
Abstract
A workstation-based real-time simulator for two-loop pressurized water reactor plants is developed for classroom training in support of a fu ll-scale simulator, on-site transient analysis, and engineering studie s. The present simulator consists of three functional modules: plant m odule, graphic module, and man-machine interaction module. The plant m odule includes models for the core kinetics, reactor coolant system, s team generator, main steam line, balance of plant, and control and pro tection system. Each of the models is optimized to obtain the capabili ty of real-time simulation. For simulating the thermal-hydraulic behav ior of the reactor coolant system in the plant module, a fully-implici t safety analysis-2/workstation (FISA-2/WS) is developed, which adopts implicit algorithms for their inherent stability and efficiency in so lving the stiff set of equations that resulted from component models. It allows the use of a larger time step than the Courant limit without any numerical instability, and it also guarantees reasonable accuracy . And the level tracking logic and the peak cladding temperature calcu lation model on the basis of the simple analytical model are used to t rack the two-phase water level in the core and to predict the cladding temperature in the uncovered region of the core under accidents, resp ectively. The graphic module is designed to provide the user with more information at a glance by dynamically displaying schematic diagrams of the systems, symbols indicating the operating status of each compon ent, trend curves, and the main control room. Especially, the CONTROL ROOM menu is designed to enable the user to perform his specific actio ns through the schematic diagrams of the main control panels in a way similar to which operators do them in the main control room for the KO -RI Nuclear Power Plant Unit 2. In each schematic diagram of five sect ions, the indicators and alarms display the various operating paramete rs, alarm signals, and trip signals, and the user can control the vari ous components by operating the corresponding switches in each section through the mouse. Also, the user can initiate his actions through va rious system diagrams. As tools for the man-machine interface, the man -machine interaction model uses a color cathode ray tube monitor, a st andard keyboard, and the mouse. The interactive communication module r eceives parameters from the user via the keyboard and mouse, and trans fers them to the plant module so as to enable the user to perform his specific actions. This module provides the user with various initiatin g events (malfunctions and manual controls) through SYSTEM, CONTROL RO OM, and ACCIDENTS menus, and thus a wide range of nuclear steam supply system transients can be easily simulated. This module also enables t he user to select one of the menu-driven graphic displays. The FISA-2/ WS is verified through comparisons with analytical solutions, separate d tests and integral tests, and predictions by RETRAN-2 and RELAP5/MOD 3. Through the various tests of FISA-2/WS, it is convincing that FISA- 2/WS can simulate most transients of the KO-RI Unit 2 with reasonable accuracy in real time.