Methodology for validation of safety parameters and fault detection and isolation
Conference
·
OSTI ID:6837249
In this paper a methodology for instrument data validation as well as fault detection and isolation, based on analytic redundancy, is presented. This work differs from previously reported work on analytic redundancy in that validation of all the main parameters of the plant heat transport loops is sought by using plant-wide instrument information. An LMFBR plant is used as a reference, and validation of the following plant parameters is considered: reactor power (Q), reactor inlet (T/sub IC/) and reactor outlet (T/sub OC/) coolant temperatures, intermediate heat exchanger (IHX) inlet (T/sub IS/) and outlet (T/sub OS/) secondary coolant temperatures, steam generator feedwater temperature (T/sub w/), steam temperature (T/sub s/) and pressure (P/sub s/), as well as primary (G/sub p/), intermediate (G/sub I/), and feedwater (G/sub w/) flow. In this paper, only validation at steady state conditions will be discussed.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6837249
- Report Number(s):
- CONF-840614-44; ON: DE84005538
- Country of Publication:
- United States
- Language:
- English
Similar Records
Validation of plant-wide data and fault identification at steady-state
Steam-assisted jet pump
Calculation of natural convection test at Phenix using the NETFLOW++ code
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6837253
Steam-assisted jet pump
Patent
·
Tue Jul 11 00:00:00 EDT 1989
·
OSTI ID:5490259
Calculation of natural convection test at Phenix using the NETFLOW++ code
Conference
·
Sun Jul 01 00:00:00 EDT 2012
·
OSTI ID:22107791
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
BOILERS
BREEDER REACTORS
CONTROL SYSTEMS
DATA ANALYSIS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT EXCHANGERS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTORS
STEAM GENERATORS
TESTING
VALIDATION
VAPOR GENERATORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
BOILERS
BREEDER REACTORS
CONTROL SYSTEMS
DATA ANALYSIS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT EXCHANGERS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTORS
STEAM GENERATORS
TESTING
VALIDATION
VAPOR GENERATORS