Development of tools and models for computational fracture assessment

Heli Talja, Kari Santaoja

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

The aim of the work presented in this paper has been to develop and test new computational tools and theoretically more sound methods for fracture mechanical analysis. The applicability of the engineering integrity assessment system MASI for evaluation of piping components has been extended. The most important motivation for the theoretical development have been the well-known fundamental limitations in the validity of J-integral, which limits its applicability in many important practical safty assessment cases. Examples are extensive plastic deformation, multimaterial structures and ascending loading paths (especially warm prestress, WPS). Further, the micromechanical Gurson model has been applied to several reactor pressure vessel materials. Special attention is paid to the transferability of Gurson model parameters from tensile test results to prediction of ductile failure behaviour of cracked structures.
Original languageEnglish
Title of host publicationRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants
Subtitle of host publicationSynthesis of achievements 1995-1998
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages177-194
ISBN (Electronic)951-38-5264-4
ISBN (Print)951-38-5263-6
Publication statusPublished - 1998
MoE publication typeA4 Article in a conference publication
EventRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995−1998 - Espoo, Finland
Duration: 7 Dec 19987 Dec 1998

Publication series

SeriesVTT Symposium
Number190
ISSN0357-9387

Conference

ConferenceRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants
CountryFinland
CityEspoo
Period7/12/987/12/98

Fingerprint

Pressure vessels
Plastic deformation
Acoustic waves

Cite this

Talja, H., & Santaoja, K. (1998). Development of tools and models for computational fracture assessment. In RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998 (pp. 177-194). Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 190
Talja, Heli ; Santaoja, Kari. / Development of tools and models for computational fracture assessment. RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo : VTT Technical Research Centre of Finland, 1998. pp. 177-194 (VTT Symposium; No. 190).
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Talja, H & Santaoja, K 1998, Development of tools and models for computational fracture assessment. in RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 190, pp. 177-194, RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants, Espoo, Finland, 7/12/98.

Development of tools and models for computational fracture assessment. / Talja, Heli; Santaoja, Kari.

RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo : VTT Technical Research Centre of Finland, 1998. p. 177-194 (VTT Symposium; No. 190).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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AB - The aim of the work presented in this paper has been to develop and test new computational tools and theoretically more sound methods for fracture mechanical analysis. The applicability of the engineering integrity assessment system MASI for evaluation of piping components has been extended. The most important motivation for the theoretical development have been the well-known fundamental limitations in the validity of J-integral, which limits its applicability in many important practical safty assessment cases. Examples are extensive plastic deformation, multimaterial structures and ascending loading paths (especially warm prestress, WPS). Further, the micromechanical Gurson model has been applied to several reactor pressure vessel materials. Special attention is paid to the transferability of Gurson model parameters from tensile test results to prediction of ductile failure behaviour of cracked structures.

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Talja H, Santaoja K. Development of tools and models for computational fracture assessment. In RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo: VTT Technical Research Centre of Finland. 1998. p. 177-194. (VTT Symposium; No. 190).