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Title: Advanced Online Flux Mapping of CANDU PHWR by Least-Squares Method

Abstract

A least-squares method that solves both the core neutronics design equations and the in-core detector response equations on the least-squares principle is presented as a new advanced online flux-mapping method for CANada Deuterium Uranium (CANDU) pressurized heavy water reactors (PHWRs). The effectiveness of the new flux-mapping method is examined in terms of online flux-mapping calculations with numerically simulated true flux distribution and detector signals and those with the actual core-follow data for the Wolsong CANDU PHWRs in Korea. The effects of core neutronics models as well as the detector failures and uncertainties of measured detector signals on the effectiveness of the least-squares flux-mapping calculations are also examined.The following results are obtained. The least-squares method predicts the flux distribution in better agreement with the simulated true flux distribution than the standard core neutronics calculations by the finite difference method (FDM) computer code without using the detector signals. The adoption of the nonlinear nodal method based on the unified nodal method formulation instead of the FDM results in a significant improvement in prediction accuracy of the flux-mapping calculations. The detector signals estimated from the least-squares flux-mapping calculations are much closer to the measured detector signals than those from the flux synthesis methodmore » (FSM), the current online flux-mapping method for CANDU reactors. The effect of detector failures is relatively small so that the plant can tolerate up to 25% of detector failures without seriously affecting the plant operation. The detector signal uncertainties aggravate accuracy of the flux-mapping calculations, yet the effects of signal uncertainties of the order of 1% standard deviation can be tolerable without seriously degrading the prediction accuracy of the least-squares method. The least-squares method is disadvantageous because it requires longer CPU time than the existing FSM. Considering ever-increasing computer speed and the improved operational safety margin of CANDU reactors gained by accurate flux-mapping calculations, however, it is concluded that the least-squares method presents an effective alternative to the existing flux-mapping method for CANDU reactors.« less

Authors:
 [1];  [1];  [2]
  1. Seoul National University (Korea, Republic of)
  2. Korea Atomic Energy Research Institute (Korea, Republic of)
Publication Date:
OSTI Identifier:
20808450
Resource Type:
Journal Article
Journal Name:
Nuclear Science and Engineering
Additional Journal Information:
Journal Volume: 150; Journal Issue: 3; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0029-5639
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCURACY; COMPUTER CODES; DESIGN; DISTRIBUTION; DOUGLAS POINT ONTARIO REACTOR; EQUATIONS; FAILURES; FINITE DIFFERENCE METHOD; FLUX SYNTHESIS; LEAST SQUARE FIT; MAPPING; NONLINEAR PROBLEMS; NUCLEAR POWER PLANTS; REACTOR OPERATION; REPUBLIC OF KOREA; SAFETY MARGINS; SIGNALS; URANIUM

Citation Formats

Hong, In Seob, Kim, Chang Hyo, and Suk, Ho Chun. Advanced Online Flux Mapping of CANDU PHWR by Least-Squares Method. United States: N. p., 2005. Web.
Hong, In Seob, Kim, Chang Hyo, & Suk, Ho Chun. Advanced Online Flux Mapping of CANDU PHWR by Least-Squares Method. United States.
Hong, In Seob, Kim, Chang Hyo, and Suk, Ho Chun. 2005. "Advanced Online Flux Mapping of CANDU PHWR by Least-Squares Method". United States.
@article{osti_20808450,
title = {Advanced Online Flux Mapping of CANDU PHWR by Least-Squares Method},
author = {Hong, In Seob and Kim, Chang Hyo and Suk, Ho Chun},
abstractNote = {A least-squares method that solves both the core neutronics design equations and the in-core detector response equations on the least-squares principle is presented as a new advanced online flux-mapping method for CANada Deuterium Uranium (CANDU) pressurized heavy water reactors (PHWRs). The effectiveness of the new flux-mapping method is examined in terms of online flux-mapping calculations with numerically simulated true flux distribution and detector signals and those with the actual core-follow data for the Wolsong CANDU PHWRs in Korea. The effects of core neutronics models as well as the detector failures and uncertainties of measured detector signals on the effectiveness of the least-squares flux-mapping calculations are also examined.The following results are obtained. The least-squares method predicts the flux distribution in better agreement with the simulated true flux distribution than the standard core neutronics calculations by the finite difference method (FDM) computer code without using the detector signals. The adoption of the nonlinear nodal method based on the unified nodal method formulation instead of the FDM results in a significant improvement in prediction accuracy of the flux-mapping calculations. The detector signals estimated from the least-squares flux-mapping calculations are much closer to the measured detector signals than those from the flux synthesis method (FSM), the current online flux-mapping method for CANDU reactors. The effect of detector failures is relatively small so that the plant can tolerate up to 25% of detector failures without seriously affecting the plant operation. The detector signal uncertainties aggravate accuracy of the flux-mapping calculations, yet the effects of signal uncertainties of the order of 1% standard deviation can be tolerable without seriously degrading the prediction accuracy of the least-squares method. The least-squares method is disadvantageous because it requires longer CPU time than the existing FSM. Considering ever-increasing computer speed and the improved operational safety margin of CANDU reactors gained by accurate flux-mapping calculations, however, it is concluded that the least-squares method presents an effective alternative to the existing flux-mapping method for CANDU reactors.},
doi = {},
url = {https://www.osti.gov/biblio/20808450}, journal = {Nuclear Science and Engineering},
issn = {0029-5639},
number = 3,
volume = 150,
place = {United States},
year = {Fri Jul 15 00:00:00 EDT 2005},
month = {Fri Jul 15 00:00:00 EDT 2005}
}