Generation IV material issues: Case SCWR

Sami Penttilä, Aki Toivonen, Laura Rissanen, Liisa Heikinheimo

Research output: Contribution to journalArticleScientificpeer-review

Abstract

Six Generation IV nuclear power concepts becoming global research topics accepted by the GenIV international forum (GIF) with common objectives of promoting technological efficiency and safety provide attractive features and demanding new challenges e.g., increased operating temperatures, higher irradiation doses, more aggressive coolants, and/or longer life expectations than GenII and GenIII plants. This paper reviews the performance of commercial candidate materials for in-core super-critical water reactor (SCWR) applications focusing on corrosion, stress corrosion cracking (SCC), and creep issues based on work within the Euratom phase 2 high performance light water reactor phase 2 (HPLWR) project. General corrosion, i.e., oxidation rate tests, and SCC tests have been done on selected iron- and nickel-based alloys at 500°C and 650°C in supercritical water (SCW) at a pressure of 25 MPa with an oxygen concentration of 125-150 ppb in all tests. Constant load creep tests have been done on selected austenitic stainless steel at 650°C in SCW at 25 MPa and 1 ppm O2 and in inert atmospheres of He and 0.1 MPa. Based on materials studies done during the HPLWR Phase2 project, current candidates for European SCWR core internals are austenitic stainless steels having sufficient oxidation and creep resistance up to 500°C or 550°C. High chromium austenitic steels and ferritic/martensitic ODS steels are considered, in longterm, for fuel rod cladding thanks to their good oxidation resistances up to 650°C.
Original languageEnglish
Pages (from-to)469-478
Number of pages10
JournalJournal of Disaster Research
Volume5
Issue number4
DOIs
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed

Fingerprint

Light water reactors
Oxidation resistance
Stress corrosion cracking
Austenitic stainless steel
Water
Creep
Corrosion
Martensitic steel
Creep resistance
Reactor cores
Austenitic steel
Ferritic steel
Nuclear energy
Coolants
Dosimetry
Chromium
Nickel
Irradiation
Iron
Oxidation

Keywords

  • GenIV
  • supercritical water
  • corrosion
  • stress corrosion cracking
  • creep
  • austenitic alloy
  • ODS steel

Cite this

Penttilä, Sami ; Toivonen, Aki ; Rissanen, Laura ; Heikinheimo, Liisa. / Generation IV material issues : Case SCWR. In: Journal of Disaster Research. 2010 ; Vol. 5, No. 4. pp. 469-478.
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Generation IV material issues : Case SCWR. / Penttilä, Sami; Toivonen, Aki; Rissanen, Laura; Heikinheimo, Liisa.

In: Journal of Disaster Research, Vol. 5, No. 4, 2010, p. 469-478.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Generation IV material issues

T2 - Case SCWR

AU - Penttilä, Sami

AU - Toivonen, Aki

AU - Rissanen, Laura

AU - Heikinheimo, Liisa

N1 - Project code: 20062

PY - 2010

Y1 - 2010

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