Monitoring Feedwater Flow Rate and Component Thermal Performance of Pressurized Water Reactors by Means of Artificial Neural Networks-Reference-Cited by-同舟云学术

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Monitoring Feedwater Flow Rate and Component Thermal Performance of Pressurized Water Reactors by Means of Artificial Neural Networks

Published:1994-07 Issue:1 Volume:107 Page:112-123
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Kavaklioglu Kadir¹,Upadhyaya Belle R.¹

Affiliation:

1. The University of Tennessee, Department of Nuclear Engineering Knoxville, Tennessee 37996-2300

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT94-A35003

Reference13 articles.

1. “Fluid Meters, Their Theory and Application,” ASME Report, p. 43, Research Committee on Fluid Meters, New York (1959).

2. E. O. DOEBELIN, Measurement Systems Applications and Design, p. 528, McGraw-Hill, New York (1983).

3. “Feedwater Flow Measurement in U.S. Nuclear Power Generation Stations,” TR-101388, Electric Power Research Institute (Nov. 1992).

4. “Thermal Performance Diagnostics Manual for Nuclear Power Plants,” NP-4990, Vols. 1-3, Electric Power Research Institute (Apr. 1987).

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