Theory based statistical interpretation of brittle fracture toughness of reactor pressure vessel steel 15XMφA and its welds

Kim Wallin (Corresponding Author), Kari Törrönen, Ralf Ahlstrand, Boris Timofeev, Vaklav Rybin, Vladimir Nikolaev, Aleksandr Morozov

Research output: Contribution to journalArticleScientificpeer-review

11 Citations (Scopus)

Abstract

The reliability of safety analysis of nuclear reactor pressure vessels is imperatively dependent upon the reliability of the fracture toughness values used in the analysis. Normally, existing fracture toughness results are analyzed with standard statistical means making use of empirically defined distribution functions for the fracture toughness. Recent developments in the theoretical modelling of cleavage fracture initiation have evolved a sounder statistical description of the macroscopic fracture toughness. It has thus become possible to make a theoretical interpretation of the scatter in brittle fracture toughness results. Here, the theoretical relations are applied to the statistical analysis of brittle fracture toughness results for the reactor pressure vessel steel 15X2M-phi-A and its welds. Based on the analysis, theoretical statistical reference curves for the steels are presented and compared to the presently used standard reference curves.
Original languageEnglish
Pages (from-to)239-246
Number of pages8
JournalNuclear Engineering and Design
Volume135
Issue number2
DOIs
Publication statusPublished - 1992
MoE publication typeA1 Journal article-refereed

Fingerprint

brittle fracture
pressure vessels
fracture toughness
Brittle fracture
Steel structures
fracture strength
Fracture toughness
Welds
vessel
steel
reactors
steels
Statistical methods
fracture initiation
Steel
nuclear reactors
curves
Nuclear reactors
Pressure vessels
statistical analysis

Keywords

  • welding

Cite this

Wallin, Kim ; Törrönen, Kari ; Ahlstrand, Ralf ; Timofeev, Boris ; Rybin, Vaklav ; Nikolaev, Vladimir ; Morozov, Aleksandr. / Theory based statistical interpretation of brittle fracture toughness of reactor pressure vessel steel 15XMφA and its welds. In: Nuclear Engineering and Design. 1992 ; Vol. 135, No. 2. pp. 239-246.
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abstract = "The reliability of safety analysis of nuclear reactor pressure vessels is imperatively dependent upon the reliability of the fracture toughness values used in the analysis. Normally, existing fracture toughness results are analyzed with standard statistical means making use of empirically defined distribution functions for the fracture toughness. Recent developments in the theoretical modelling of cleavage fracture initiation have evolved a sounder statistical description of the macroscopic fracture toughness. It has thus become possible to make a theoretical interpretation of the scatter in brittle fracture toughness results. Here, the theoretical relations are applied to the statistical analysis of brittle fracture toughness results for the reactor pressure vessel steel 15X2M-phi-A and its welds. Based on the analysis, theoretical statistical reference curves for the steels are presented and compared to the presently used standard reference curves.",
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Theory based statistical interpretation of brittle fracture toughness of reactor pressure vessel steel 15XMφA and its welds. / Wallin, Kim (Corresponding Author); Törrönen, Kari; Ahlstrand, Ralf; Timofeev, Boris; Rybin, Vaklav; Nikolaev, Vladimir; Morozov, Aleksandr.

In: Nuclear Engineering and Design, Vol. 135, No. 2, 1992, p. 239-246.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Theory based statistical interpretation of brittle fracture toughness of reactor pressure vessel steel 15XMφA and its welds

AU - Wallin, Kim

AU - Törrönen, Kari

AU - Ahlstrand, Ralf

AU - Timofeev, Boris

AU - Rybin, Vaklav

AU - Nikolaev, Vladimir

AU - Morozov, Aleksandr

N1 - Project code: MET00132

PY - 1992

Y1 - 1992

N2 - The reliability of safety analysis of nuclear reactor pressure vessels is imperatively dependent upon the reliability of the fracture toughness values used in the analysis. Normally, existing fracture toughness results are analyzed with standard statistical means making use of empirically defined distribution functions for the fracture toughness. Recent developments in the theoretical modelling of cleavage fracture initiation have evolved a sounder statistical description of the macroscopic fracture toughness. It has thus become possible to make a theoretical interpretation of the scatter in brittle fracture toughness results. Here, the theoretical relations are applied to the statistical analysis of brittle fracture toughness results for the reactor pressure vessel steel 15X2M-phi-A and its welds. Based on the analysis, theoretical statistical reference curves for the steels are presented and compared to the presently used standard reference curves.

AB - The reliability of safety analysis of nuclear reactor pressure vessels is imperatively dependent upon the reliability of the fracture toughness values used in the analysis. Normally, existing fracture toughness results are analyzed with standard statistical means making use of empirically defined distribution functions for the fracture toughness. Recent developments in the theoretical modelling of cleavage fracture initiation have evolved a sounder statistical description of the macroscopic fracture toughness. It has thus become possible to make a theoretical interpretation of the scatter in brittle fracture toughness results. Here, the theoretical relations are applied to the statistical analysis of brittle fracture toughness results for the reactor pressure vessel steel 15X2M-phi-A and its welds. Based on the analysis, theoretical statistical reference curves for the steels are presented and compared to the presently used standard reference curves.

KW - welding

U2 - 10.1016/0029-5493(92)90225-K

DO - 10.1016/0029-5493(92)90225-K

M3 - Article

VL - 135

SP - 239

EP - 246

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 2

ER -