Published April 2009 | Version v1
Miscellaneous

Improved core protection calculator system algorithm

  • 1. Korea Nuclear Fuel, Daejeon (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
  • 3. Doosan Heavy Industries and Construction Co., Ltd., Yongin (Korea, Republic of)

Description

Core Protection Calculator System (CPCS) is a digitized core protection system which provides core protection functions based on two reactor core operation parameters, Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD). It generates a reactor trip signal when the core condition exceeds the DNBR or LPD design limit. It consists of four independent channels which adapted a two out of four trip logic. CPCS algorithm improvement for the newly designed core protection calculator system, RCOPS (Reactor COre Protection System), is described in this paper. New features include the improvement of DNBR algorithm for thermal margin, the addition of pre trip alarm generation for auxiliary trip function, VOPT (Variable Over Power Trip) prevention during RPCS (Reactor Power Cutback System) actuation and the improvement of CEA (Control Element Assembly) signal checking algorithm. To verify the improved CPCS algorithm, CPCS algorithm verification tests, 'Module Test' and 'Unit Test', would be performed on RCOPS single channel facility. It is expected that the improved CPCS algorithm will increase DNBR margin and enhance the plant availability by reducing unnecessary reactor trips

Part of:
Proceedings of the 24th KAIF/KNS Annual Conference

Additional details

Publishing Information

Publisher
KAIF-KNS
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the 24th KAIF/KNS Annual Conference
Imprint Pagination
667 p.
Journal Page Range
p. 475-480

Conference

Title
24. KAIF/KNS Annual Conference
Dates
8-10 Apr 2009
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44066882
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ALGORITHMS; COMPUTER CALCULATIONS; CONTROL ELEMENTS; DESIGN; POWER DENSITY; REACTOR CORES; SAFETY
Descriptors DEC
MATHEMATICAL LOGIC; REACTOR COMPONENTS

Optional Information

Notes
4 refs, 5 figs