Corrosion Studies of Candidate Materials for European HPLWR

Sami Penttilä, Aki Toivonen, Liisa Heikinheimo, Radek Novotny

Research output: Contribution to journalArticleScientificpeer-review

10 Citations (Scopus)

Abstract

The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; however, the material requirements for HPLWR offer challenges because of the extreme operating temperatures and pressures. Consequently, general corrosion rates were studied in water at 300 to 650°C at supercritical pressure using weight gain measurements. Oxide thicknesses were determined from cross-section samples. The compositions of the oxide layers were analyzed using scanning electron microscopy in conjuction with energy dispersive spectroscopy. The surface layers of selected samples were analyzed also by X-ray diffraction. The test matrix included ten materials from four alloy classes: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. A high oxidation resistance was seen in Ni-base alloy 625, austenitic stainless steels with high Cr content (>18 wt% Cr), and an ODS steel containing 20% Cr at all applied test temperatures (300 to 650°C). The oxidation rates of austenitic stainless steels with lower Cr content, 15 to 18%, increase considerably at temperatures >500°C. The oxidation rates of 9% Cr ODS steels were moderate or high at all temperatures. Ferritic/martensitic steels showed high oxidation rates at all temperatures.
Original languageEnglish
Pages (from-to)261-271
Number of pages11
JournalNuclear Technology
Volume170
Issue number1
DOIs
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed

Fingerprint

Light water reactors
Corrosion
Austenitic stainless steel
Oxides
Martensitic steel
Ferritic steel
Oxidation
Steel
Temperature
Gain measurement
Oxidation resistance
Weighing
Corrosion rate
Energy dispersive spectroscopy
Nickel
X ray diffraction
Scanning electron microscopy
Chemical analysis
Water

Keywords

  • SCWR
  • general corrosion
  • candidate alloys

Cite this

Penttilä, Sami ; Toivonen, Aki ; Heikinheimo, Liisa ; Novotny, Radek. / Corrosion Studies of Candidate Materials for European HPLWR. In: Nuclear Technology. 2010 ; Vol. 170, No. 1. pp. 261-271.
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abstract = "The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; however, the material requirements for HPLWR offer challenges because of the extreme operating temperatures and pressures. Consequently, general corrosion rates were studied in water at 300 to 650°C at supercritical pressure using weight gain measurements. Oxide thicknesses were determined from cross-section samples. The compositions of the oxide layers were analyzed using scanning electron microscopy in conjuction with energy dispersive spectroscopy. The surface layers of selected samples were analyzed also by X-ray diffraction. The test matrix included ten materials from four alloy classes: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. A high oxidation resistance was seen in Ni-base alloy 625, austenitic stainless steels with high Cr content (>18 wt{\%} Cr), and an ODS steel containing 20{\%} Cr at all applied test temperatures (300 to 650°C). The oxidation rates of austenitic stainless steels with lower Cr content, 15 to 18{\%}, increase considerably at temperatures >500°C. The oxidation rates of 9{\%} Cr ODS steels were moderate or high at all temperatures. Ferritic/martensitic steels showed high oxidation rates at all temperatures.",
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Corrosion Studies of Candidate Materials for European HPLWR. / Penttilä, Sami; Toivonen, Aki; Heikinheimo, Liisa; Novotny, Radek.

In: Nuclear Technology, Vol. 170, No. 1, 2010, p. 261-271.

Research output: Contribution to journalArticleScientificpeer-review

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AU - Penttilä, Sami

AU - Toivonen, Aki

AU - Heikinheimo, Liisa

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AB - The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; however, the material requirements for HPLWR offer challenges because of the extreme operating temperatures and pressures. Consequently, general corrosion rates were studied in water at 300 to 650°C at supercritical pressure using weight gain measurements. Oxide thicknesses were determined from cross-section samples. The compositions of the oxide layers were analyzed using scanning electron microscopy in conjuction with energy dispersive spectroscopy. The surface layers of selected samples were analyzed also by X-ray diffraction. The test matrix included ten materials from four alloy classes: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. A high oxidation resistance was seen in Ni-base alloy 625, austenitic stainless steels with high Cr content (>18 wt% Cr), and an ODS steel containing 20% Cr at all applied test temperatures (300 to 650°C). The oxidation rates of austenitic stainless steels with lower Cr content, 15 to 18%, increase considerably at temperatures >500°C. The oxidation rates of 9% Cr ODS steels were moderate or high at all temperatures. Ferritic/martensitic steels showed high oxidation rates at all temperatures.

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KW - general corrosion

KW - candidate alloys

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