On the simulation of two-phase flow pressurized thermal shock (PTS)

D. Lucas (Corresponding author), D. Bestion, E. Bodèle, M. Scheuerer, F. D'Auria, D. Mazzini, B. Smith, I. Tiselj, A. Martin, D. Lakehal, J.-M. Seynhave, R. Kyrki-Rajamäki, Mikko Ilvonen, J. Macek

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

12 Citations (Scopus)

Abstract

This paper reports some activity about the Pressurized Thermal Shock (PTS) performed within the European Integrated Project NURESIM.
The PTS phenomenon is expected to take place in some water cooled nuclear reactors equipped with pressure vessels during selected accident scenarios.
The PTS implies 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. Current generation Pressurized Water Reactors, PWR (including the Russian VVER types), are primarily affected by the phenomenon which is investigated within three broad areas: material damage originated by irradiation, thermal-hydraulics (including single and two-phase flow conditions in the region of the ‘shock’) and structural mechanics with main reference to fracture mechanics.
The present paper, in the area of thermal-hydraulics, focuses on the study of two-phase conditions that are potentially at the origin of PTS. Within the above context, the paper summarizes recent advances in the understanding of the two-phase phenomena occurring within the geometric region of the nuclear reactor, i.e. 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 mechanisms (or 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 (case of two phase flow) is presently not available.
Original languageEnglish
Title of host publicationProceedings
Subtitle of host publication12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
PublisherCurran Associates Inc.
Pages358-379
ISBN (Print)978-1-6056-0071-0
Publication statusPublished - 2007
MoE publication typeA4 Article in a conference publication
Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 - Pittsburgh, United States
Duration: 30 Sep 20073 Oct 2007

Conference

Conference12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
CountryUnited States
CityPittsburgh
Period30/09/073/10/07

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