Nickel‐based alloy corrosion in CANDU steam generators: E–pH diagrams of the Ni–NH3–H2O and Ni–CH3COO–H2O ternary systems

Author:

Khollari Mohammad Amin Razmjoo1ORCID,Zebardast Hamid2,Asselin Edouard1

Affiliation:

1. Department of Materials Engineering The University of British Columbia British Columbia Canada

2. Forensic and Component Services Materials and Major Components, Kinectrics Inc. Ontario Canada

Abstract

AbstractNuclear power plant steam generator (SG) tubes contain nickel as the main alloying element and there is concern about their corrosion. We optimized models for calculating the high‐temperature and high‐pressure thermodynamic properties of common nuclear alloy elements. Subsequently, we calculated the E–pH diagrams for nickel in different concentrations of ammonia or acetate ion at temperatures ranging from 100°C to 260°C and a pressure of 4.7 MPa. This information is used to predict the corrosion behavior of nickel in the secondary circuit conditions of Canadian Deuterium Uranium (CANDU) SGs. Increasing the ammonia or acetate ion concentration resulted in the predominance of Ni(NH3)n2+ or Ni(Ac)n(2−n) at the expense of Ni2+ and NiO, indicating a higher risk of nickel corrosion. Calculations showed that under normal operating conditions with [NH3]tot = 5 × 10−5 and [CH3COO]tot = 10−8 m at 260°C and 4.7 MPa, nickel will be passivated as NiO, preventing the rapid degradation of nickel‐based alloys. However, in the presence of a crevice that allows the acetate ion to concentrate, nickel would dissolve in the form of the Ni2+ ion, endangering safe operation of CANDU SGs.

Publisher

Wiley

Subject

Materials Chemistry,Metals and Alloys,Surfaces, Coatings and Films,Mechanical Engineering,Mechanics of Materials,Environmental Chemistry,Materials Chemistry,Metals and Alloys,Surfaces, Coatings and Films,Mechanical Engineering,Mechanics of Materials,Environmental Chemistry,Materials Chemistry,Metals and Alloys,Surfaces, Coatings and Films,Mechanical Engineering,Mechanics of Materials,Environmental Chemistry

Reference56 articles.

1. M.Naraine J.Riznic inInternational Conference on Nuclear Engineering Proceedings ICONE25‐66001 American Society of Mechanical Engineers Shanghai China2017 p.V009T15A001.

2. Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: a review

3. Materials performance in CANDU reactors: The first 30 years and the prognosis for life extension and new designs

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