Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant

Arja Saarenheimo, Lauri Eerikäinen, Rauli Keskinen

Research output: Contribution to journalArticleScientificpeer-review

Abstract

A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30% may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.
Original languageEnglish
Pages (from-to)41-55
Number of pages15
JournalRakenteiden Mekaniikka
Volume27
Issue number2
Publication statusPublished - 1994
MoE publication typeNot Eligible

Fingerprint

Nuclear power plants
Pipe
Water
Structural dynamics
ABAQUS
Stress-strain curves
Dynamic analysis
Momentum
Hydraulics
Boundary conditions
Fluxes
Fluids
Hot Temperature
Uncertainty

Cite this

Saarenheimo, Arja ; Eerikäinen, Lauri ; Keskinen, Rauli. / Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant. In: Rakenteiden Mekaniikka. 1994 ; Vol. 27, No. 2. pp. 41-55.
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abstract = "A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30{\%} may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.",
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Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant. / Saarenheimo, Arja; Eerikäinen, Lauri; Keskinen, Rauli.

In: Rakenteiden Mekaniikka, Vol. 27, No. 2, 1994, p. 41-55.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Dynamic post-analysis of a feed water pipe at the Loviisa nuclear power plant

AU - Saarenheimo, Arja

AU - Eerikäinen, Lauri

AU - Keskinen, Rauli

N1 - Project code: VAL37051

PY - 1994

Y1 - 1994

N2 - A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30% may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.

AB - A dynamic post-analysis is presented for a sudden pipe break which occurTed in the main feed water ~ystem of the VVER 440 type PWR plant Loviisa 2 on February 25, 1993. A thermal hydraulic code TMOC, based on the method of characteristics, is first used to determine the induced rapid two phase fluid transients. The resulting pressure and momentum flux histories are then applied as an excitation in a nonlinear structural dynamic analysis which makes use of the general purpose finite element code ABAQUS. The permanent relative displacement of the broken pipe ends is finally compared with the value observed after the event. An underestimate of some 30% may for the most part be attributed to scant experimental data and uncertainties in boundary conditions. Assumptions regarding impact against a nearby beam structure and the dynamic stress-strain curve of the fenitic pipe material strongly affect this comparison.

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