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dc.contributor.authorDu Rand, C.P.
dc.contributor.authorVan Schoor, G.
dc.date.accessioned2013-10-24T10:46:09Z
dc.date.available2013-10-24T10:46:09Z
dc.date.issued2012
dc.identifier.citationDu Rand, C.P. & Van Schoor, G. 2012. Fault diagnosis of generation IV nuclear HTGR components. Part 2. The area error enthalpy-entropy graph approach. Annals of nuclear energy, 41(1):79-86. [https://doi.org/10.1016/j.anucene.2011.11.009]en_US
dc.identifier.issn0306-4549
dc.identifier.issn1873-2100 (Online)
dc.identifier.urihttp://hdl.handle.net/10394/9360
dc.identifier.urihttps://www.sciencedirect.com/science/article/pii/S0306454911004373
dc.identifier.urihttps://doi.org/10.1016/j.anucene.2011.11.009
dc.description.abstractThe second paper in a two part series presents the area error method for generation of representative enthalpy–entropy (h–s) fault signatures to classify malfunctions in generation IV nuclear high temperature gas-cooled reactor (HTGR) components. The second classifier is devised to ultimately address the fault diagnosis (FD) problem via the proposed methods in a multiple classifier (MC) ensemble. FD is realized by way of different input feature sets to the classification algorithm based on the area and trajectory of the residual shift between the fault-free and the actual operating h–s graph models. The application of the proposed technique is specifically demonstrated for 24 single fault transients considered in the main power system (MPS) of the Pebble Bed Modular Reactor (PBMR). The results show that the area error technique produces different fault signatures with low correlation for all the examined component faults. A brief evaluation of the two fault signature generation techniques is presented and the performance of the area error method is documented using the fault classification index (FCI) presented in Part I of the series. The final part of this work reports the application of the proposed approach for classification of an emulated fault transient in data from the prototype Pebble Bed Micro Model (PBMM) plant. Reference data values are calculated for the plant via a thermo-hydraulic simulation model of the MPS. The results show that the correspondence between the fault signatures, generated via experimental plant data and simulated reference values, are generally good. The work presented in the two part series, related to the classification of component faults in the MPS of different HTGRs, suggest that the proposed h–s graph approach provides a suitable FD framework for generation IV nuclear energy systems.en_US
dc.language.isoenen_US
dc.publisherElsevieren_US
dc.subjectEnthalpy-entropy (h-s)en_US
dc.subjectfault diagnosisen_US
dc.subjecthigh temperature gas-cooled reactor (HTGR)en_US
dc.subjectnuclearen_US
dc.subjectPebble Bed Modular Reactor (PBMR)en_US
dc.subjectPebble Bed Micro Model (PBMM)en_US
dc.titleFault diagnosis of generation IV nuclear HTGR components. Part 2. The area error enthalpy-entropy graph approachen_US
dc.typeArticleen_US
dc.contributor.researchID11790199 - Du Rand, Carel Petrus
dc.contributor.researchID12134457 - Van Schoor, George


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