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 language | English (US) |
|---|---|
| Pages (from-to) | 468-482 |
| Number of pages | 15 |
| Journal | Nuclear Science and Engineering |
| Volume | 121 |
| Issue number | 3 |
| DOIs | |
| State | Published - Jan 1 1995 |
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All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
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Modeling water chemistry, electrochemical corrosion potential, and crack growth rate in the boiling water reactor heat transport circuits - I : the damage-predictor algorithm. / Yeh, Tsung Kuang; Macdonald, Digby D.; Motta, Arthur Thompson.
In: Nuclear Science and Engineering, Vol. 121, No. 3, 01.01.1995, p. 468-482.Research output: Contribution to journal › Article
TY - JOUR
T1 - Modeling water chemistry, electrochemical corrosion potential, and crack growth rate in the boiling water reactor heat transport circuits - I
T2 - the damage-predictor algorithm
AU - Yeh, Tsung Kuang
AU - Macdonald, Digby D.
AU - Motta, Arthur Thompson
PY - 1995/1/1
Y1 - 1995/1/1
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=0029406351&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=0029406351&partnerID=8YFLogxK
U2 - 10.13182/NSE95-A24148
DO - 10.13182/NSE95-A24148
M3 - Article
AN - SCOPUS:0029406351
VL - 121
SP - 468
EP - 482
JO - Nuclear Science and Engineering
JF - Nuclear Science and Engineering
SN - 0029-5639
IS - 3
ER -