Modeling water chemistry, electrochemical corrosion potential, and crack growth rate in the boiling water reactor heat transport circuits - I: the damage-predictor algorithm

Tsung Kuang Yeh, Digby D. Macdonald, Arthur T. Motta

Research output: Contribution to journalArticle

42 Scopus citations

Abstract

A computer code with the capability of simultaneously estimating the concentrations of radiolysis species, the electrochemical corrosion potential, and the kinetics of growth of a reference crack in sensitized Type 304 stainless steel is developed for the heat transport circuits of boiling water reactors (BWRs). The primary objective of this code, DAMAGE-PREDICTOR, is to theoretically evaluate the effectiveness of hydrogen water chemistry (HWC) in the BWRs as a function of feedwater hydrogen concentration and reactor power level. The power level determines various important thermal-hydraulic parameters and the neutron and gamma energy deposition rate in the core and near-core regions. These input parameters are estimated using well-established algorithms, and the simulations are carried out for full-power conditions for two reactors that differ markedly in their responses to HWC. The DAMAGE-PREDICTOR code is found to successfully account for plant data from both reactors using a single set of model parameter values.

Original languageEnglish (US)
Pages (from-to)468-482
Number of pages15
JournalNuclear Science and Engineering
Volume121
Issue number3
DOIs
StatePublished - Jan 1 1995

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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