Comparative analyses concerning integrity of a VVER-440 reactor pressure vessel

Jurgen Sievers, X Liu, Pentti Rajamäki, Heli Talja, Heikki Raiko

Research output: Contribution to journalArticleScientific

6 Citations (Scopus)

Abstract

Comparative analyses have been performed with 3-D finite element (FE) models for a six loop cladded reactor pressure vessel with an assumed circumferential surface crack. In the analyses, a thermomechanical transient due to a loss of coolant with high pressure injection has been considered.
The transient is characterized by an axisymmetric cooling phase which is followed by an asymmetric, strip-like cooling period. For the fracture assessment, stress intensity factors calculated from local J-integral values have been compared. It has been shown that with different FE programs and meshes, the crack loading can be calculated within a 10% scatter.
Furthermore, simplified fracture methods show a much larger scatter, mainly due to approximation of the non-linear stress distribution by membrane and bending stress.
Original languageEnglish
Pages (from-to)63-68
JournalNuclear Engineering and Design
Volume159
Issue number1
DOIs
Publication statusPublished - 1995
MoE publication typeB1 Article in a scientific magazine

Fingerprint

pressure vessels
Pressure vessels
integrity
vessel
reactors
loss of coolant
J integral
Cooling
Cracks
cooling
surface cracks
stress intensity factors
crack
Stress intensity factors
Coolants
stress distribution
Stress concentration
mesh
strip
cracks

Cite this

Sievers, Jurgen ; Liu, X ; Rajamäki, Pentti ; Talja, Heli ; Raiko, Heikki. / Comparative analyses concerning integrity of a VVER-440 reactor pressure vessel. In: Nuclear Engineering and Design. 1995 ; Vol. 159, No. 1. pp. 63-68.
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Comparative analyses concerning integrity of a VVER-440 reactor pressure vessel. / Sievers, Jurgen; Liu, X; Rajamäki, Pentti; Talja, Heli; Raiko, Heikki.

In: Nuclear Engineering and Design, Vol. 159, No. 1, 1995, p. 63-68.

Research output: Contribution to journalArticleScientific

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T1 - Comparative analyses concerning integrity of a VVER-440 reactor pressure vessel

AU - Sievers, Jurgen

AU - Liu, X

AU - Rajamäki, Pentti

AU - Talja, Heli

AU - Raiko, Heikki

PY - 1995

Y1 - 1995

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AB - Comparative analyses have been performed with 3-D finite element (FE) models for a six loop cladded reactor pressure vessel with an assumed circumferential surface crack. In the analyses, a thermomechanical transient due to a loss of coolant with high pressure injection has been considered. The transient is characterized by an axisymmetric cooling phase which is followed by an asymmetric, strip-like cooling period. For the fracture assessment, stress intensity factors calculated from local J-integral values have been compared. It has been shown that with different FE programs and meshes, the crack loading can be calculated within a 10% scatter. Furthermore, simplified fracture methods show a much larger scatter, mainly due to approximation of the non-linear stress distribution by membrane and bending stress.

U2 - 10.1016/0029-5493(95)01055-M

DO - 10.1016/0029-5493(95)01055-M

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