MODELING WATER CHEMISTRY, ELECTROCHEMICAL CORROSION POTENTIAL, AND CRACK-GROWTH RATE IN THE BOILING WATER-REACTOR HEAT-TRANSPORT CIRCUITS .1. THE DAMAGE-PREDICTOR ALGORITHM
Tk. Yeh et al., MODELING WATER CHEMISTRY, ELECTROCHEMICAL CORROSION POTENTIAL, AND CRACK-GROWTH RATE IN THE BOILING WATER-REACTOR HEAT-TRANSPORT CIRCUITS .1. THE DAMAGE-PREDICTOR ALGORITHM, Nuclear science and engineering, 121(3), 1995, pp. 468-482
A computer code with the capability of simultaneously estimating the c
oncentrations of radiolysis species, the electrochemical corrosion pot
ential, 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 hy
drogen water chemistry (HWC) in the BWRs as a function of feedwater hy
drogen concentration and reactor power level. The power level determin
es 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 reac
tors that differ markedly in their responses to HWC. The DAMAGE-PREDIC
TOR code is found to successfully account for plant data from both rea
ctors using a single set of model parameter values.