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

Magnus Boåsen; Pål Efsing; Ulla Ehrnstén

doi:10.1016/j.jnucmat.2016.11.026

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

Magnus Boåsen, Pål Efsing, Ulla Ehrnstén

KTH Royal Institute of Technology

Research output: Contribution to journal › Article › Scientific › peer-review

8 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 language	English
Pages (from-to)	110-119
Journal	Journal of Nuclear Materials
Volume	484
DOIs	https://doi.org/10.1016/j.jnucmat.2016.11.026
Publication status	Published - 2017
MoE publication type	A1 Journal article-refereed

Keywords

nuclear
pressure vessel steel
embrittlement
hardness

Access to Document

10.1016/j.jnucmat.2016.11.026

Cite this

@article{edd510e3a52e4549b2fe5c1c6d1e09cc,

title = "On flux effects in a low alloy steel from a Swedish reactor pressure vessel",

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.",

keywords = "nuclear, pressure vessel steel, embrittlement, hardness",

author = "Magnus Bo{\aa}sen and P{\aa}l Efsing and Ulla Ehrnst{\'e}n",

note = "Funding Information: This investigation has been funded by a grant from The Swedish Radiation Safety Authority (SSM). An appreciation is directed to NUGENIA + for the young scientist short training grant that made travelling to VTT for experiments possible, grant agreement no: 604965. The authors are also deeply grateful for the assistance in the experimental effort by the laboratory staff M.Sc. Petteri Lappalainen, Mr. Arto Kukkonen, Mrs. Marketta Mattila and Mr. Jari Lydman at VTT in Espoo, Finland. Publisher Copyright: {\textcopyright} 2016 Elsevier B.V. Copyright: Copyright 2017 Elsevier B.V., All rights reserved.",

year = "2017",

doi = "10.1016/j.jnucmat.2016.11.026",

language = "English",

volume = "484",

pages = "110--119",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

}

TY - JOUR

T1 - On flux effects in a low alloy steel from a Swedish reactor pressure vessel

AU - Boåsen, Magnus

AU - Efsing, Pål

AU - Ehrnstén, Ulla

N1 - Funding Information: This investigation has been funded by a grant from The Swedish Radiation Safety Authority (SSM). An appreciation is directed to NUGENIA + for the young scientist short training grant that made travelling to VTT for experiments possible, grant agreement no: 604965. The authors are also deeply grateful for the assistance in the experimental effort by the laboratory staff M.Sc. Petteri Lappalainen, Mr. Arto Kukkonen, Mrs. Marketta Mattila and Mr. Jari Lydman at VTT in Espoo, Finland. Publisher Copyright: © 2016 Elsevier B.V. Copyright: Copyright 2017 Elsevier B.V., All rights reserved.

PY - 2017

Y1 - 2017

N2 - 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.

AB - 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.

KW - nuclear

KW - pressure vessel steel

KW - embrittlement

KW - hardness

UR - http://www.scopus.com/inward/record.url?scp=85002170882&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2016.11.026

DO - 10.1016/j.jnucmat.2016.11.026

M3 - Article

SN - 0022-3115

VL - 484

SP - 110

EP - 119

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

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

Abstract

Keywords

Access to Document

Other files and links

Fingerprint

Cite this