Published September 2014 | Version v1
Journal article

Sensitivity analysis of CHF parameters under flow instability by using a neural network method

  • 1. Nuclear Safety and Thermal Power Standardization Institute, North China Electric Power University, Changping District, Beijing 102206 (China)
  • 2. CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Chengdu 610041, Sichuan Province (China)

Description

Highlights: • We constructed the predicting model of CHF based on BP neural network. • We found the sensitivity coefficients of different parameters. • We got the comprehensive effect influence of different parameters to CHF. - Abstract: Construct the predicting model of CHF based on BP neural network. The sensitivity coefficients of different parameters could be calculated by solving partial differential of the predicting model. With the method of neural network connection weight sensitivity analysis and the data from other researchers' experiments, the sensitivity of different factors to the critical heat flux (CHF) is analyzed. The result shows that, ΔGmax/G0 has the largest sensitivity coefficients to CHF and the inlet temperature has the smallest sensitivity coefficients in the test range. The sensitivity of ΔGmax/G0 could be 20 times of that of the inlet temperature. The BP predictions of CHF fit well with the experimental data, and the errors fall in the margin of 5%. The BP predictions of the influences of ΔGmax/G0 and τ to CFm fit well with Kim's formula, and the largest error is 12.5%

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2014.03.040

Additional details

Identifiers

DOI
10.1016/j.anucene.2014.03.040;
PII
S0306-4549(14)00162-5;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
71
Journal Page Range
p. 211-216
ISSN
0306-4549
CODEN
ANENDJ

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46022060
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
CRITICAL HEAT FLUX; ERRORS; EXPERIMENTAL DATA; FLOW MODELS; NEURAL NETWORKS; PARTIAL DIFFERENTIAL EQUATIONS; SENSITIVITY ANALYSIS
Descriptors DEC
DATA; DIFFERENTIAL EQUATIONS; EQUATIONS; HEAT FLUX; INFORMATION; MATHEMATICAL MODELS; NUMERICAL DATA

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.