On flux effects in a low alloy steel from a Swedish reactor pressure vessel

Magnus Boåsen, Pål Efsing, Ulla Ehrnstén

Research output: Contribution to journalArticleScientificpeer-review

3 Citations (Scopus)

Abstract

This study aims to investigate the presence of Unstable Matrix Defects in irradiated pressure vessel steel from weldments of the Swedish PWR Ringhals 4 (R4). Hardness tests have been performed on low flux (surveillance material) and high flux (Halden reactor) irradiated material samples in combination with heat treatments at temperatures of 330, 360 and 390 °C in order to reveal eventual recovery of any hardening features induced by irradiation. The experiments carried out in this study could not reveal any hardness recovery related to Unstable Matrix Defects at relevant temperatures. However, a difference in hardness recovery was found between the low and the high flux samples at heat treatments at higher temperatures than expected for the annihilation of Unstable Matrix Defects–the observed recovery is here attributed to differences of the solute clusters formed by the high and low flux irradiations.

Original languageEnglish
Pages (from-to)110-119
Number of pages10
JournalJournal of Nuclear Materials
Volume484
DOIs
Publication statusPublished - 2017
MoE publication typeA1 Journal article-refereed

Fingerprint

pressure vessels
high strength steels
Pressure vessels
High strength steel
recovery
reactors
Fluxes
Recovery
Hardness
Halden Boiling Water Reactor
heat treatment
hardness
matrices
reactor materials
Heat treatment
Irradiation
hardness tests
Defects
irradiation
defects

Keywords

  • nuclear
  • pressure vessel steel
  • embrittlement
  • hardness

Cite this

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On flux effects in a low alloy steel from a Swedish reactor pressure vessel. / Boåsen, Magnus; Efsing, Pål; Ehrnstén, Ulla.

In: Journal of Nuclear Materials, Vol. 484, 2017, p. 110-119.

Research output: Contribution to journalArticleScientificpeer-review

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