An overview of the pressurized thermal shock issue in the context of the NURESIM project

D. Lucas (Corresponding Author), D. Bestion, E. Bodéle, P. Coste, M. Scheuerer, F. D’Auria, D. Mazzini, B. Smith, I. Tiselj, A. Martin, D. Lakehal, J.M. Seynhaeve, R. Kyrki-Rajamäki, Mikko Ilvonen, J. Macek

Research output: Contribution to journalArticleScientificpeer-review

31 Citations (Scopus)

Abstract

Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident scenarios for Pressurized Water Reactors may cause Emergency Core Coolant injection into the cold leg leading to PTS situations. They imply the formation of temperature gradients in the thick vessel walls with consequent localized stresses and the potential for propagation of possible flaws present in the material. This paper focuses on two-phase conditions that are potentially at the origin of PTS. It summarizes recent advances in the understanding of the two-phase phenomena occurring within the geometric region of the nuclear reactor,that is, the cold leg and the downcomer, where the “PTS fluid-dynamics" is relevant. Available experimental data for validation of two-phase CFD simulation tools are reviewed and the capabilities of such tools to capture each basic phenomenon are discussed. Key conclusions show that several two-phase flow subphenomena are involved and can individually be simulated at least at a qualitative level, but the capability to simulate their interaction and the overall system performance is still limited. In the near term, one may envisage a simplified treatment of two-phase PTS transients by neglecting some effects which are not yet well controlled, leading to slightly conservative predictions.
Original languageEnglish
Article number583259
Number of pages13
JournalScience and Technology of Nuclear Installations
Volume2009
DOIs
Publication statusPublished - 2009
MoE publication typeA1 Journal article-refereed

Fingerprint

Thermal shock
Pressurized water reactors
Nuclear reactors
Fluid dynamics
Two phase flow
Coolants
Thermal gradients
Accidents
Computational fluid dynamics
Defects

Cite this

Lucas, D., Bestion, D., Bodéle, E., Coste, P., Scheuerer, M., D’Auria, F., ... Macek, J. (2009). An overview of the pressurized thermal shock issue in the context of the NURESIM project. Science and Technology of Nuclear Installations, 2009, [583259]. https://doi.org/10.1155/2009/583259
Lucas, D. ; Bestion, D. ; Bodéle, E. ; Coste, P. ; Scheuerer, M. ; D’Auria, F. ; Mazzini, D. ; Smith, B. ; Tiselj, I. ; Martin, A. ; Lakehal, D. ; Seynhaeve, J.M. ; Kyrki-Rajamäki, R. ; Ilvonen, Mikko ; Macek, J. / An overview of the pressurized thermal shock issue in the context of the NURESIM project. In: Science and Technology of Nuclear Installations. 2009 ; Vol. 2009.
@article{48f78a62c1ec463987876f8cb04e2522,
title = "An overview of the pressurized thermal shock issue in the context of the NURESIM project",
abstract = "Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident scenarios for Pressurized Water Reactors may cause Emergency Core Coolant injection into the cold leg leading to PTS situations. They imply the formation of temperature gradients in the thick vessel walls with consequent localized stresses and the potential for propagation of possible flaws present in the material. This paper focuses on two-phase conditions that are potentially at the origin of PTS. It summarizes recent advances in the understanding of the two-phase phenomena occurring within the geometric region of the nuclear reactor,that is, the cold leg and the downcomer, where the “PTS fluid-dynamics{"} is relevant. Available experimental data for validation of two-phase CFD simulation tools are reviewed and the capabilities of such tools to capture each basic phenomenon are discussed. Key conclusions show that several two-phase flow subphenomena are involved and can individually be simulated at least at a qualitative level, but the capability to simulate their interaction and the overall system performance is still limited. In the near term, one may envisage a simplified treatment of two-phase PTS transients by neglecting some effects which are not yet well controlled, leading to slightly conservative predictions.",
author = "D. Lucas and D. Bestion and E. Bod{\'e}le and P. Coste and M. Scheuerer and F. D’Auria and D. Mazzini and B. Smith and I. Tiselj and A. Martin and D. Lakehal and J.M. Seynhaeve and R. Kyrki-Rajam{\"a}ki and Mikko Ilvonen and J. Macek",
year = "2009",
doi = "10.1155/2009/583259",
language = "English",
volume = "2009",
journal = "Science and Technology of Nuclear Installations",
issn = "1687-6075",
publisher = "Hindawi",

}

Lucas, D, Bestion, D, Bodéle, E, Coste, P, Scheuerer, M, D’Auria, F, Mazzini, D, Smith, B, Tiselj, I, Martin, A, Lakehal, D, Seynhaeve, JM, Kyrki-Rajamäki, R, Ilvonen, M & Macek, J 2009, 'An overview of the pressurized thermal shock issue in the context of the NURESIM project', Science and Technology of Nuclear Installations, vol. 2009, 583259. https://doi.org/10.1155/2009/583259

An overview of the pressurized thermal shock issue in the context of the NURESIM project. / Lucas, D. (Corresponding Author); Bestion, D.; Bodéle, E.; Coste, P.; Scheuerer, M.; D’Auria, F.; Mazzini, D.; Smith, B.; Tiselj, I.; Martin, A.; Lakehal, D.; Seynhaeve, J.M.; Kyrki-Rajamäki, R.; Ilvonen, Mikko; Macek, J.

In: Science and Technology of Nuclear Installations, Vol. 2009, 583259, 2009.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - An overview of the pressurized thermal shock issue in the context of the NURESIM project

AU - Lucas, D.

AU - Bestion, D.

AU - Bodéle, E.

AU - Coste, P.

AU - Scheuerer, M.

AU - D’Auria, F.

AU - Mazzini, D.

AU - Smith, B.

AU - Tiselj, I.

AU - Martin, A.

AU - Lakehal, D.

AU - Seynhaeve, J.M.

AU - Kyrki-Rajamäki, R.

AU - Ilvonen, Mikko

AU - Macek, J.

PY - 2009

Y1 - 2009

N2 - Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident scenarios for Pressurized Water Reactors may cause Emergency Core Coolant injection into the cold leg leading to PTS situations. They imply the formation of temperature gradients in the thick vessel walls with consequent localized stresses and the potential for propagation of possible flaws present in the material. This paper focuses on two-phase conditions that are potentially at the origin of PTS. It summarizes recent advances in the understanding of the two-phase phenomena occurring within the geometric region of the nuclear reactor,that is, the cold leg and the downcomer, where the “PTS fluid-dynamics" is relevant. Available experimental data for validation of two-phase CFD simulation tools are reviewed and the capabilities of such tools to capture each basic phenomenon are discussed. Key conclusions show that several two-phase flow subphenomena are involved and can individually be simulated at least at a qualitative level, but the capability to simulate their interaction and the overall system performance is still limited. In the near term, one may envisage a simplified treatment of two-phase PTS transients by neglecting some effects which are not yet well controlled, leading to slightly conservative predictions.

AB - Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident scenarios for Pressurized Water Reactors may cause Emergency Core Coolant injection into the cold leg leading to PTS situations. They imply the formation of temperature gradients in the thick vessel walls with consequent localized stresses and the potential for propagation of possible flaws present in the material. This paper focuses on two-phase conditions that are potentially at the origin of PTS. It summarizes recent advances in the understanding of the two-phase phenomena occurring within the geometric region of the nuclear reactor,that is, the cold leg and the downcomer, where the “PTS fluid-dynamics" is relevant. Available experimental data for validation of two-phase CFD simulation tools are reviewed and the capabilities of such tools to capture each basic phenomenon are discussed. Key conclusions show that several two-phase flow subphenomena are involved and can individually be simulated at least at a qualitative level, but the capability to simulate their interaction and the overall system performance is still limited. In the near term, one may envisage a simplified treatment of two-phase PTS transients by neglecting some effects which are not yet well controlled, leading to slightly conservative predictions.

U2 - 10.1155/2009/583259

DO - 10.1155/2009/583259

M3 - Article

VL - 2009

JO - Science and Technology of Nuclear Installations

JF - Science and Technology of Nuclear Installations

SN - 1687-6075

M1 - 583259

ER -