A Signal Validation Methodology for Nuclear Power Plants

James C. Deckert; Jay L. Fisher; David B. Laning; Asok Ray

doi:10.23919/acc.1982.4787816

A Signal Validation Methodology for Nuclear Power Plants

James C. Deckert, Jay L. Fisher, David B. Laning, Asok Ray

Mechanical Engineering

Research output: Contribution to journal › Conference article › peer-review

2 Scopus citations

Abstract

A signal validation methodology to improve the reliability of the information displayed to the operator of a nuclear power plant is presented. The general design methodology is developed and then applied to the steam generator and feedwater subsystem of a typical pressurized water reactor. Using steady-state and transient simulations of this subsystem, including realistic additive sensor noise, the developed algorithm successfully isolates a variety of injected sensor faults and demonstrates its inherent capability to isolate common-mode sensor failures and plant component failures.

Original language	English (US)
Article number	4787816
Pages (from-to)	113-120
Number of pages	8
Journal	Proceedings of the American Control Conference
Volume	1982-June
DOIs	https://doi.org/10.23919/acc.1982.4787816
State	Published - 1982
Event	1st American Control Conference, ACC 1982 - Arlington, United States Duration: Jun 14 1982 → Jun 16 1982

All Science Journal Classification (ASJC) codes

Electrical and Electronic Engineering

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10.23919/acc.1982.4787816

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title = "A Signal Validation Methodology for Nuclear Power Plants",

abstract = "A signal validation methodology to improve the reliability of the information displayed to the operator of a nuclear power plant is presented. The general design methodology is developed and then applied to the steam generator and feedwater subsystem of a typical pressurized water reactor. Using steady-state and transient simulations of this subsystem, including realistic additive sensor noise, the developed algorithm successfully isolates a variety of injected sensor faults and demonstrates its inherent capability to isolate common-mode sensor failures and plant component failures.",

author = "Deckert, {James C.} and Fisher, {Jay L.} and Laning, {David B.} and Asok Ray",

note = "Funding Information: The work reported in this paper was sponsored by the Electric Power Research Institute through Combustion Engineering, Inc., Contract 11680. The authors qratefully acknowledge the data and technical insiqhts provided by various C-E personnel, includinq C.T. French, J.N. Lanzalotta, G.M. Meijer, d.P. Pasquenza, and F.J. Safryn; and the contributions of their Draper Laboratory colleagues, M.N. Desai and J.J Deyst. Publisher Copyright: {\textcopyright} 1982 AACC.; 1st American Control Conference, ACC 1982 ; Conference date: 14-06-1982 Through 16-06-1982",

year = "1982",

doi = "10.23919/acc.1982.4787816",

language = "English (US)",

volume = "1982-June",

pages = "113--120",

journal = "Proceedings of the American Control Conference",

issn = "0743-1619",

publisher = "Institute of Electrical and Electronics Engineers Inc.",

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TY - JOUR

T1 - A Signal Validation Methodology for Nuclear Power Plants

AU - Deckert, James C.

AU - Fisher, Jay L.

AU - Laning, David B.

AU - Ray, Asok

N1 - Funding Information: The work reported in this paper was sponsored by the Electric Power Research Institute through Combustion Engineering, Inc., Contract 11680. The authors qratefully acknowledge the data and technical insiqhts provided by various C-E personnel, includinq C.T. French, J.N. Lanzalotta, G.M. Meijer, d.P. Pasquenza, and F.J. Safryn; and the contributions of their Draper Laboratory colleagues, M.N. Desai and J.J Deyst. Publisher Copyright: © 1982 AACC.

PY - 1982

Y1 - 1982

N2 - A signal validation methodology to improve the reliability of the information displayed to the operator of a nuclear power plant is presented. The general design methodology is developed and then applied to the steam generator and feedwater subsystem of a typical pressurized water reactor. Using steady-state and transient simulations of this subsystem, including realistic additive sensor noise, the developed algorithm successfully isolates a variety of injected sensor faults and demonstrates its inherent capability to isolate common-mode sensor failures and plant component failures.

AB - A signal validation methodology to improve the reliability of the information displayed to the operator of a nuclear power plant is presented. The general design methodology is developed and then applied to the steam generator and feedwater subsystem of a typical pressurized water reactor. Using steady-state and transient simulations of this subsystem, including realistic additive sensor noise, the developed algorithm successfully isolates a variety of injected sensor faults and demonstrates its inherent capability to isolate common-mode sensor failures and plant component failures.

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U2 - 10.23919/acc.1982.4787816

DO - 10.23919/acc.1982.4787816

M3 - Conference article

AN - SCOPUS:84941509966

SN - 0743-1619

VL - 1982-June

SP - 113

EP - 120

JO - Proceedings of the American Control Conference

JF - Proceedings of the American Control Conference

M1 - 4787816

T2 - 1st American Control Conference, ACC 1982

Y2 - 14 June 1982 through 16 June 1982

ER -

A Signal Validation Methodology for Nuclear Power Plants

Abstract

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