Expert system for the CPCS-initiated trip analysis

Conference · Tue Jan 01 04:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5978008

Sohn, Sedo; Im, Inyoung; Kuh, Jungeui ^[1]

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1. Korea Atomic Energy Research Inst., Taejon (Korea)

In Yonggwang nuclear units 3 and 4, the core protection calculator system (CPCS) performs various protection logics against many transients and certain accidents. The CPCS is a real-time computer system calculating the departure from nucleate boiling ratio (DNBR), and local power density, and other protection logics. It takes process variables such as neutron flux, hot-leg temperature, cold-leg temperature, control element assembly positions, and reactor coolant pump shaft speed. Since the CPCS protection logics are quite complex, it is difficult for an operator to tell immediately which parameter is the major cause of the reactor trip. Thus, whenever the reactor trip signal is generated, the process input variables and calculated results, including selected intermediate variables, are frozen in the specified computer memory for later analysis. These frozen variables are called the trip buffer. Analysis of the trip buffer requires an expert in the CPCS and related documents containing algorithms and a data base for algorithms. The Trip Buffer Analysis Program (TBAP) is an expert system that pinpoints the causes of the CPCS initiated reactor trip, thus relieving the operator from the burden of analyzing the trip buffer.

• OSTI ID: 5978008
• Report Number(s): CONF-910603--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
• Country of Publication: United States
• Language: English

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ACCIDENTS
ALGORITHMS
BOILING
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COOLING SYSTEMS
DATA BASE MANAGEMENT
DEPARTURE NUCLEATE BOILING
DESIGN
DIAGNOSTIC TECHNIQUES
DOCUMENTATION
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EXPERT SYSTEMS
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MATHEMATICAL LOGIC
NEUTRON FLUX
NUCLEATE BOILING
PERFORMANCE
PERSONNEL
PHASE TRANSFORMATIONS
POWER DENSITY
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PROGRAMMING
PWR TYPE REACTORS
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATORS
REACTOR PROTECTION SYSTEMS
REACTOR SHUTDOWN
REACTORS
REAL TIME SYSTEMS
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TESTING
THERMAL REACTORS
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WATER MODERATED REACTORS