(A) study on design of the trip computer for ECCS based on dynamic safety system = 동적안전계통 기능을 가진 비상노심냉각계통 트립컴퓨터 설계에 관한 연구

Cited 0 time in webofscience Cited 0 time in scopus
  • Hit : 314
  • Download : 0
The Emergency Core Cooling system in current nuclear power plants typically has a considerable number of complex functions and largely cumbersome operator interfaces. Functions for initiation, switch-over between various phases of operation, interlocks, monitoring, and alarming are usually performed by relay and analog comparator logic which is difficult to maintain and test. To improve problems of an analog based ECC (Emergency Core Cooling) System, the trip computer for ECCS based on Dynamic Safety System is implemented. The Dynamic Safety System (DSS) is a computer based reactor protection system that has fail-safe nature and performs a dynamic self-testing. The most important feature of the DSS is the introduction of test signal that send the system into a tripped state. The test signals are interleaved between the plant signals to produce an output which switches between a tripped and health state. The dynamic operation is a key feature of the failsafe design of the system. In this thesis, a possible implementation of the DSS using PLC is presented for a CANDU reactor. ECC System of the CANDU Reactor is selected as the reference system. The function of the DSS is implemented In PLC with the CONCEPT language. CONCEPT was developed by GROUPE SCHNEIDER as a graphic user interface programming tool for the Quantum PLC. A MMI display for ECCS based on DSS is implemented with LOOKOUT as an object driven programming tool. The Validation test has been performed by S/W Input Simulator as per Validation Test Procedure. The result of the test was checked and displayed on the MMI display. From the test results, it is shown that the DSS based ECC System operates correctly in all conditions.
Advisors
Seong, Poong-Hyunresearcher성풍현researcher
Description
한국과학기술원 : 원자력공학과,
Publisher
한국과학기술원
Issue Date
2000
Identifier
158107/325007 / 000973104
Language
eng
Description

학위논문(석사) - 한국과학기술원 : 원자력공학과, 2000.2, [ vii, 62 p. ]

URI
http://hdl.handle.net/10203/49410
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=158107&flag=dissertation
Appears in Collection
NE-Theses_Master(석사논문)
Files in This Item
There are no files associated with this item.

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0