Compact analyzer for BWR (Boiling Water Reactor) applications: Final report

Technical Report · Sat Aug 01 04:00:00 EDT 1987

OSTI ID:6260712

May, R S

Experiences of recent years have demonstrated the need for utilities operating nuclear power plants to effectively analyze operational transient events and to train their staffs to understand the basic features of such events. The EPRI program to develop a Company Analyzer combines modeling capabilities of the EPRI Modular Modeling System (MMS) with real-time graphic display capabilities of the EPRI Information Monitoring and Applied Graphics Environment (IMAGE). The result is an integrated system which: (a) allows a user to interactively define transient events and perform important control functions; (b) performs transient analyses on a host minicomputer; and (c) updates colorgraphic displays in real-time to present the results. The Boiling Water Reactor (BWR) Compact Analyzer includes a plant model representing the BWR core and vessel, important control and protection systems, and balance of plant including feedwater heaters, high and low pressure turbines and extraction lines. As an option, the user may choose to model only the nuclear steam supply system, with the balance of plant interfaces treated only as boundary conditions. A set of color displays was developed which includes mimics of the vessel, balance of plant, and safety systems, as well as a system overview display and time-plots of key parameters. The architecture of the Compact Analyzer system is documented in detail. This project has culminated in a prototype system demonstrating the Compact Analyzer for Boiling Water Reactor applications.

• Research Organization: Levy (S.), Inc., Campbell, CA (USA); Electric Power Research Inst., Palo Alto, CA (USA)
• OSTI ID: 6260712
• Report Number(s): EPRI-NP-5366; ON: TI87920581
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
CONTROL SYSTEMS
DISPLAY DEVICES
REACTOR CONTROL SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
REAL TIME SYSTEMS
SIMULATION
SYSTEMS ANALYSIS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS