Computer modeling for boiling water reactors on radiolysis, ECP, and crack growth rates
- Inst. of Nuclear Energy Research, Lung-Tan (Taiwan, Province of China). Div. of Nuclear Fuel and Materials
- Pennsylvania State Univ., University Park, PA (United States). Center for Advanced Materials
The limited accessibility of boiling water reactors (BWRs) has made it difficult or sometimes impossible to monitor the development of material damage inside these reactors. Material damage in BWRs usually occurs in the form of intergranular stress corrosion cracking (IGSCC) and irradiation assisted stress corrosion cracking (IASCC), due to the presence of strongly oxidizing species, such as oxygen and hydrogen peroxide. These species are produced in or near the reactor core by the irradiation of water by neutrons and gamma photons. By calculating the concentrations of the radiolysis species, which in turn determine the ECP and the crack growth rate in the heat transport circuits (HTCs) of BWRs, the author are able to predict the rate at which damage develops throughout the entire HTCs of BWRs. A computer code has been developed for modeling the development of material damage in the BWRs. The algorithm of the code contains facilities for estimating the concentrations of radiolysis products (in particular O{sub 2}, H{sub 2}, and H{sub 2}O{sub 2}), the electrochemical corrosion potential (ECP), and the kinetics of growth of a reference crack in sensitized Type 304SS around the HTCs. After calibrating the model against plant data from Dresden-2, the code is able to successfully account for the oxygen concentration and the ECP in the recirculation system of Duane Arnold.
- OSTI ID:
- 367747
- Report Number(s):
- CONF-960389-; TRN: IM9640%%493
- Resource Relation:
- Conference: National Association of Corrosion Engineers (NACE) annual corrosion conference and exposition: water and waste water industries, Denver, CO (United States), 24-29 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of Corrosion/96 conference papers; PB: [6615] p.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
REACTOR COOLING SYSTEMS
CRACK PROPAGATION
PHYSICAL RADIATION EFFECTS
STRESS CORROSION
DUANE ARNOLD-1 REACTOR
BWR TYPE REACTORS
D CODES
DRESDEN-2 REACTOR
STAINLESS STEEL-304
REACTOR MATERIALS
INTERGRANULAR CORROSION
WATER CHEMISTRY
THEORETICAL DATA