Modeling the development of damage in BWR primary coolant circuits
- Pennsylvania State Univ., University Park, PA (United States). Center for Advanced Materials
Hydrogen water chemistry (HWC) has been explored as a remedial measure for inhibiting intergranular stress corrosion cracking (IGSCC), and for recently for mitigating irradiation assisted stress corrosion cracking (IASCC) in boiling water reactors over the past ten years. However, it is not clear if HWC can successfully protect all of the structural components in BWR primary heat transport circuits (HTCS) from IGSCC and LASCC. The authors have explored this issue using DAMAGE-PREDICTOR, which is a computer code that is capable of estimating the concentrations of radiolysis species, the electrochemical corrosion potential (ECP), and the growth rate of a reference crack in sensitized Type 304 stainless steel. This code was developed specifically for modeling the HTCs of BWRs. The primary objective of this code is to theoretically evaluate the effectiveness of HWC in BWRs as a function of feedwater hydrogen concentration and reactor power level. HWC simulations have been carried out for full power conditions for two reactors that differ markedly in their responses to HWC. It is found that DAMAGE-PREDICTOR can successfully account for plant data from both reactors using a single set of model parameter values.
- OSTI ID:
- 203762
- Report Number(s):
- CONF-950816-; ISBN 1-877914-95-9; TRN: 96:009728
- Resource Relation:
- Conference: 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995; Other Information: PBD: 1995; Related Information: Is Part Of Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2; Airey, G.; Andresen, P.; Brown, J. [eds.] [and others]; PB: 620 p.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
WATER CHEMISTRY
STAINLESS STEEL-304
PHYSICAL RADIATION EFFECTS
STRESS CORROSION
CRACK PROPAGATION
INTERGRANULAR CORROSION
MITIGATION
MATHEMATICAL MODELS
D CODES
THEORETICAL DATA
COMPUTERIZED SIMULATION