Determination of thermal-hydraulic loads on reactor internals in a DBA-situation

Ville Lestinen; Timo Toppila; Antti Timperi; Timo Pättikangas; Markku Hänninen

doi:10.1115/PVP2006-ICPVT-11-93456

Determination of thermal-hydraulic loads on reactor internals in a DBA-situation

Ville Lestinen, Timo Toppila, Antti Timperi, Timo Pättikangas, Markku Hänninen

Fortum Waste Solutions Oy

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

3 Citations (Scopus)

Abstract

According to Finnish regulatory requirements, reactor internals have to stay intact in design basis accident (DBA) situations, so that control rods can always penetrate into the core. This is the basic motivation to study and develop more detailed methods for analyses of thermal-hydraulic loads on reactor internals during the DBA situation. In this work, the studied accident situation is Large Break Loss of Coolant Accident (LBLOCA). The objective of this work is to connect thermal-hydraulic and mechanical analysis methods with the goal to produce a reliable method for determination of thermal-hydraulic and mechanical loads on reactor internals in the accident situation. In the present model, the downcomer of a PWR is only included and the reactor internals will be added later. The tools studied are thermal-hydraulic system codes, computational fluid dynamics (CFD) codes and finite element analysis (FEA) codes. Both thermal-hydraulic and mechanical aspects are discussed in this paper. Firstly, the pressure boundary condition in the pipe break point was calculated with the system code. In the second step, CFD analyses were made. Finally, the full fluid-structure interaction coupling between the CFD and FEA codes was used.

Original language	English
Title of host publication	ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference Proceedings
Publisher	American Society of Mechanical Engineers (ASME)
Pages	1539-1548
Volume	4
ISBN (Print)	0-7918-4755-1
DOIs	https://doi.org/10.1115/PVP2006-ICPVT-11-93456
Publication status	Published - 2006
MoE publication type	A4 Article in a conference publication
Event	ASME Pressure Vessels and Piping Conference, PVP 2006: Held jointly with the 11th International Conference on Pressure Vessel Technology, ICPVT-11 - Vancouver, Canada Duration: 23 Jul 2006 → 27 Jul 2006

Conference

Conference	ASME Pressure Vessels and Piping Conference, PVP 2006
Country/Territory	Canada
City	Vancouver
Period	23/07/06 → 27/07/06

Keywords

Large-Break LOCA
LBLOCA
loss of coolant accident
PWR
fluid-structure interaction
FSI

Access to Document

10.1115/PVP2006-ICPVT-11-93456

Cite this

Lestinen, V., Toppila, T., Timperi, A., Pättikangas, T., & Hänninen, M. (2006). Determination of thermal-hydraulic loads on reactor internals in a DBA-situation. In ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference Proceedings (Vol. 4, pp. 1539-1548). Article PVP2006-ICPVT-11-93456 American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/PVP2006-ICPVT-11-93456

@inproceedings{c0084c68301f45e9b08654df82dd5c3b,

title = "Determination of thermal-hydraulic loads on reactor internals in a DBA-situation",

abstract = "According to Finnish regulatory requirements, reactor internals have to stay intact in design basis accident (DBA) situations, so that control rods can always penetrate into the core. This is the basic motivation to study and develop more detailed methods for analyses of thermal-hydraulic loads on reactor internals during the DBA situation. In this work, the studied accident situation is Large Break Loss of Coolant Accident (LBLOCA). The objective of this work is to connect thermal-hydraulic and mechanical analysis methods with the goal to produce a reliable method for determination of thermal-hydraulic and mechanical loads on reactor internals in the accident situation. In the present model, the downcomer of a PWR is only included and the reactor internals will be added later. The tools studied are thermal-hydraulic system codes, computational fluid dynamics (CFD) codes and finite element analysis (FEA) codes. Both thermal-hydraulic and mechanical aspects are discussed in this paper. Firstly, the pressure boundary condition in the pipe break point was calculated with the system code. In the second step, CFD analyses were made. Finally, the full fluid-structure interaction coupling between the CFD and FEA codes was used.",

keywords = "Large-Break LOCA, LBLOCA, loss of coolant accident, PWR, fluid-structure interaction, FSI",

author = "Ville Lestinen and Timo Toppila and Antti Timperi and Timo P{\"a}ttikangas and Markku H{\"a}nninen",

note = "Project code: G5SU01114 Project code: C5SU00793; ASME Pressure Vessels and Piping Conference, PVP 2006 : Held jointly with the 11th International Conference on Pressure Vessel Technology, ICPVT-11 ; Conference date: 23-07-2006 Through 27-07-2006",

year = "2006",

doi = "10.1115/PVP2006-ICPVT-11-93456",

language = "English",

isbn = "0-7918-4755-1 ",

volume = "4",

pages = "1539--1548",

booktitle = "ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference Proceedings",

publisher = "American Society of Mechanical Engineers (ASME)",

address = "United States",

}

Lestinen, V, Toppila, T, Timperi, A , Pättikangas, T & Hänninen, M 2006, Determination of thermal-hydraulic loads on reactor internals in a DBA-situation. in ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference Proceedings. vol. 4, PVP2006-ICPVT-11-93456, American Society of Mechanical Engineers (ASME), pp. 1539-1548, ASME Pressure Vessels and Piping Conference, PVP 2006, Vancouver, British Columbia, Canada, 23/07/06. https://doi.org/10.1115/PVP2006-ICPVT-11-93456

Determination of thermal-hydraulic loads on reactor internals in a DBA-situation. / Lestinen, Ville; Toppila, Timo; Timperi, Antti et al.
ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference Proceedings. Vol. 4 American Society of Mechanical Engineers (ASME), 2006. p. 1539-1548 PVP2006-ICPVT-11-93456.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Determination of thermal-hydraulic loads on reactor internals in a DBA-situation

AU - Lestinen, Ville

AU - Toppila, Timo

AU - Timperi, Antti

AU - Pättikangas, Timo

AU - Hänninen, Markku

N1 - Project code: G5SU01114 Project code: C5SU00793

PY - 2006

Y1 - 2006

N2 - According to Finnish regulatory requirements, reactor internals have to stay intact in design basis accident (DBA) situations, so that control rods can always penetrate into the core. This is the basic motivation to study and develop more detailed methods for analyses of thermal-hydraulic loads on reactor internals during the DBA situation. In this work, the studied accident situation is Large Break Loss of Coolant Accident (LBLOCA). The objective of this work is to connect thermal-hydraulic and mechanical analysis methods with the goal to produce a reliable method for determination of thermal-hydraulic and mechanical loads on reactor internals in the accident situation. In the present model, the downcomer of a PWR is only included and the reactor internals will be added later. The tools studied are thermal-hydraulic system codes, computational fluid dynamics (CFD) codes and finite element analysis (FEA) codes. Both thermal-hydraulic and mechanical aspects are discussed in this paper. Firstly, the pressure boundary condition in the pipe break point was calculated with the system code. In the second step, CFD analyses were made. Finally, the full fluid-structure interaction coupling between the CFD and FEA codes was used.

AB - According to Finnish regulatory requirements, reactor internals have to stay intact in design basis accident (DBA) situations, so that control rods can always penetrate into the core. This is the basic motivation to study and develop more detailed methods for analyses of thermal-hydraulic loads on reactor internals during the DBA situation. In this work, the studied accident situation is Large Break Loss of Coolant Accident (LBLOCA). The objective of this work is to connect thermal-hydraulic and mechanical analysis methods with the goal to produce a reliable method for determination of thermal-hydraulic and mechanical loads on reactor internals in the accident situation. In the present model, the downcomer of a PWR is only included and the reactor internals will be added later. The tools studied are thermal-hydraulic system codes, computational fluid dynamics (CFD) codes and finite element analysis (FEA) codes. Both thermal-hydraulic and mechanical aspects are discussed in this paper. Firstly, the pressure boundary condition in the pipe break point was calculated with the system code. In the second step, CFD analyses were made. Finally, the full fluid-structure interaction coupling between the CFD and FEA codes was used.

KW - Large-Break LOCA

KW - LBLOCA

KW - loss of coolant accident

KW - PWR

KW - fluid-structure interaction

KW - FSI

U2 - 10.1115/PVP2006-ICPVT-11-93456

DO - 10.1115/PVP2006-ICPVT-11-93456

M3 - Conference article in proceedings

SN - 0-7918-4755-1

VL - 4

SP - 1539

EP - 1548

BT - ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference Proceedings

PB - American Society of Mechanical Engineers (ASME)

T2 - ASME Pressure Vessels and Piping Conference, PVP 2006

Y2 - 23 July 2006 through 27 July 2006

ER -

Determination of thermal-hydraulic loads on reactor internals in a DBA-situation

Abstract

Conference

Keywords

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