Change search
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf
Pre-Test Simulations of SIMECO-2 Experiments on Stratified Melt Pool Heat Transfer
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety. KTH.ORCID iD: 0000-0003-0408-8807
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0001-8148-9423
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0003-3132-7252
Show others and affiliations
2016 (English)Conference paper, Published paper (Refereed)
Abstract [en]

Severe accident progression in light water reactors can lead to the formation of a melt pool in the lower head that can impose thermo-mechanical loads on the pressure vessel, and subsequently can lead to vessel failure. For quantification of the thermal load which is important to in-vessel corium coolability and retention, various experiments have been carried out to investigate the heat transfer characteristics of melt pools, including the SIMECO experiment accomplished at KTH (Sehgal et al., 1998), which used low melting-point materials as the simulant of corium. In order to reduce the gaps in temperature and scale between experimental and prototypical conditions, a new test facility named SIMECO-2 is being designed at KTH (supported by the EU project IVMR), which features higher temperature (up to 900 ℃℃) and larger scale (1 meter in diameter), aiming to investigate the natural convection heat transfer of a stratified melt pool and the effects of different parameters/factors such as temperature of melt, thickness of boundary crust, thickness of top layer, top layer cooling. The present study is to provide pre-test calculations using the PECM method (Tran and Dinh, 2009), with the objectives to provide insights and analytical support to the design of the SIMECO-2 facility, including determination of required input power, as well as estimate of the temperature and heat flux distributions in the layers and time to reach steady state mode. A calculation was first performed for a reference base case with one-layer pool for which a CFD simulation was also conducted as benchmark. The calculations were then carried on to investigate the influences of different boundary conditions and internal heat sources on heat transfer. Finally the thermal behavior of a two-layer melt pool configuration was addressed in detail, and suggestions for the experimental conditions were provided.

Place, publisher, year, edition, pages
2016. article id N11P0585
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-259588OAI: oai:DiVA.org:kth-259588DiVA, id: diva2:1352343
Conference
The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11)
Note

QC 20191021

Available from: 2019-09-18 Created: 2019-09-18 Last updated: 2019-10-21Bibliographically approved

Open Access in DiVA

No full text in DiVA

Authority records BETA

Yu, PengKomlev, Andrei A.Villanueva, WalterMa, WeiminBechta, Sevostian

Search in DiVA

By author/editor
Yu, PengKomlev, Andrei A.Villanueva, WalterMa, WeiminBechta, Sevostian
By organisation
Nuclear Power Safety
Energy Engineering

Search outside of DiVA

GoogleGoogle Scholar

urn-nbn

Altmetric score

urn-nbn
Total: 52 hits
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf