Effect of thermal ageing on impact ductility of the nuclear reactor pressure vessel steel SA533B and its weld metal

Reijo Pelli, Jarl Forsten

Research output: Contribution to journalArticleScientificpeer-review

4 Citations (Scopus)

Abstract

The effects of long term thermal ageing on the impact toughness of a reactor pressure vessel (RPV) steel SA533B and its submerged arc weld metal have been studied.
The annealings were carried out at 350–450 °C with a duration of 1–5 years. An estimate of the degree of embrittlement at the expected end-of-life of a RPV was made. The studied base metal did not exhibit any noticeable embrittlement during the anticipated reactor life. The studied weld metal proved to be susceptible to the thermal ageing resulting in a small rise in the ductile-brittle transition temperature at the expected end-of-life of the reactor pressure vessel.
Original languageEnglish
Pages (from-to)25-31
JournalTheoretical and Applied Fracture Mechanics
Volume8
Issue number1
DOIs
Publication statusPublished - 1987
MoE publication typeA1 Journal article-refereed

Fingerprint

Nuclear Reactor
Thermal aging
pressure vessels
Ductility
nuclear reactors
Steel structures
Nuclear reactors
ductility
Vessel
Reactor
Steel
Welds
Metals
reactors
Embrittlement
steels
Pressure vessels
embrittlement
metals
ductile-brittle transition

Keywords

  • nuclear reactors

Cite this

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abstract = "The effects of long term thermal ageing on the impact toughness of a reactor pressure vessel (RPV) steel SA533B and its submerged arc weld metal have been studied. The annealings were carried out at 350–450 °C with a duration of 1–5 years. An estimate of the degree of embrittlement at the expected end-of-life of a RPV was made. The studied base metal did not exhibit any noticeable embrittlement during the anticipated reactor life. The studied weld metal proved to be susceptible to the thermal ageing resulting in a small rise in the ductile-brittle transition temperature at the expected end-of-life of the reactor pressure vessel.",
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Effect of thermal ageing on impact ductility of the nuclear reactor pressure vessel steel SA533B and its weld metal. / Pelli, Reijo; Forsten, Jarl.

In: Theoretical and Applied Fracture Mechanics, Vol. 8, No. 1, 1987, p. 25-31.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Effect of thermal ageing on impact ductility of the nuclear reactor pressure vessel steel SA533B and its weld metal

AU - Pelli, Reijo

AU - Forsten, Jarl

PY - 1987

Y1 - 1987

N2 - The effects of long term thermal ageing on the impact toughness of a reactor pressure vessel (RPV) steel SA533B and its submerged arc weld metal have been studied. The annealings were carried out at 350–450 °C with a duration of 1–5 years. An estimate of the degree of embrittlement at the expected end-of-life of a RPV was made. The studied base metal did not exhibit any noticeable embrittlement during the anticipated reactor life. The studied weld metal proved to be susceptible to the thermal ageing resulting in a small rise in the ductile-brittle transition temperature at the expected end-of-life of the reactor pressure vessel.

AB - The effects of long term thermal ageing on the impact toughness of a reactor pressure vessel (RPV) steel SA533B and its submerged arc weld metal have been studied. The annealings were carried out at 350–450 °C with a duration of 1–5 years. An estimate of the degree of embrittlement at the expected end-of-life of a RPV was made. The studied base metal did not exhibit any noticeable embrittlement during the anticipated reactor life. The studied weld metal proved to be susceptible to the thermal ageing resulting in a small rise in the ductile-brittle transition temperature at the expected end-of-life of the reactor pressure vessel.

KW - nuclear reactors

U2 - 10.1016/0167-8442(87)90015-2

DO - 10.1016/0167-8442(87)90015-2

M3 - Article

VL - 8

SP - 25

EP - 31

JO - Theoretical and Applied Fracture Mechanics

JF - Theoretical and Applied Fracture Mechanics

SN - 0167-8442

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