Published 1997 | Version v1
Miscellaneous

Sensor calibration and monitoring using auto associative neural networks

  • 1. Honeywell Technology Center, Minneapolis, MN (United States)
  • 2. Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering
  • 3. Oak Ridge National Lab., TN (United States). Instrumentation and Control Div.

Description

The approach to instrument surveillance and calibration verification (ISCV) through plant wide monitoring proposed in this paper is the use of an auto associative neural network (AANN) which will utilize digitized data presently available in the Safety Parameter Display computer system from Florida Power Corporation Crystal River 3 nuclear power plant. An auto associative neural network is one in which the outputs are trained to emulate the inputs over an appropriate dynamic range. The relationships between the different variables are embedded in the weights by the training process. As a result, the output can be a correct version of an input pattern that has been distorted by noise, missing data, or non-linearities. Plant variables that have some degree of coherence with each other constitute the inputs to the network. Once the network has been trained with normal operational data using a robust training procedures, it has been shown to successfully monitor the selected plant variables to detect sensor drift or failure by simply comparing the network inputs with the outputs using a sequential probability ratio test (SPRT).The AANN method of monitoring many variables not only indicates that there is a sensor failure, it clearly indicates the signal channel in which the signal error has occurred. (author). 6 refs., 5 figs., 2 tabs

Part of:
Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics

Additional details

Publishing Information

Imprint Title
Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics
Imprint Pagination
838 p.
Journal Page Range
p. 322-327.

Conference

Title
Meeting on reactor physics and thermal hydraulics.
Acronym
11. ENFIR
Dates
18-22 Aug 1997.
Place
Pocos de Caldas, MG (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
28075968
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ARTIFICIAL INTELLIGENCE; NEURAL NETWORKS; NUCLEAR ENGINEERING; REACTOR CONTROL SYSTEMS; REACTOR INSTRUMENTATION; REACTOR MONITORING SYSTEMS; REACTOR OPERATION; REACTOR TECHNOLOGY; REACTORS
Descriptors DEC
CONTROL SYSTEMS; ENGINEERING; OPERATION

Optional Information

Notes
Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.