MODELING WATER CHEMISTRY, ELECTROCHEMICAL CORROSION POTENTIAL, AND CRACK-GROWTH RATE IN THE BOILING WATER-REACTOR HEAT-TRANSPORT CIRCUITS .1. THE DAMAGE-PREDICTOR ALGORITHM

被引:37
作者
YEH, TK
MACDONALD, DD
MOTTA, AT
机构
[1] Pennsylvania State Univ, University Park, PA
关键词
D O I
10.13182/NSE95-A24148
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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.
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页码:468 / 482
页数:15
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