title: Development of a cause analysis system for a CPCS trip by using the rule-base deduction method.
abstract: A Core Protection Calculator System (CPCS) was developed to initiate a Reactor Trip under the circumstance of certain transients by a Combustion Engineering Company. The major function of the Core Protection Calculator System is to generate contact outputs for the Departure from Nucleate Boiling Ratio (DNBR) Trip and a Local Power Density (LPD) Trip. But in a Core Protection Calculator System, a trip cause cannot be identified, thus only trip signals are transferred to the Plant Protection System (PPS) and only the trip status is displayed. It could take a considerable amount of time and effort for a plant operator to analyze the trip causes of a Core Protection Calculator System. So, a Cause Analysis System for a Core Protection Calculator System (CASCPCS) has been developed by using the rule-base deduction method to assist operators in a Nuclear Power Plant. CASCPCS consists of three major parts. Inference engine has a role of controlling the searching knowledge base, executing the rules and tracking the inference process by using the depth-first searching method. Knowledge base consists of four major parts: rules, data base constants, trip buffer variables and causes. And a user interface is implemented by using menu-driven and window display techniques. The advantage of CASCPCS is that it saves time and effort to diagnose the trip causes of a Core Protection Calculator System, it increases a plant's availability and reliability, and it makes it easy to manage CASCPCS because of using only a cursor control.
authors.affiliation: I&C HFE Department, Korea Atomic Energy Research Institute, Yuseong, Daejeon, Republic of Korea. parkjy1@kaeri.re.kr
authors.forename: Je-Yun
authors.initials: JY
authors.lastname: Park
authors.forename: In-Soo
authors.initials: IS
authors.lastname: Koo
authors.forename: Chang-Ho
authors.initials: CH
authors.lastname: Sohn
authors.forename: Jung-Seon
authors.initials: JS
authors.lastname: Kim
authors.forename: Gi-Ho
authors.initials: GH
authors.lastname: Cho
authors.forename: Hee-Seok
authors.initials: HS
authors.lastname: Park
mesh_terms: D000465:Algorithms; D003198:Computer Simulation; D003661:Decision Support Techniques; D004868:Equipment Failure; D019544:Equipment Failure Analysis; D005246:Feedback; D008962:Models, Theoretical; D009688:Nuclear Reactors / Q000295:instrumentation*; D011786:Quality Control