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Validation of a full model for the analysis of ex-vessel steam explosion in LWRs
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-0683-9136
2019 (English)In: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, p. 4568-4574Conference paper, Published paper (Refereed)
Abstract [en]

In a Light Water Reactor (LWR) severe accident, the reactor core can be melted and released from the reactor vessel at ~3000K. In most of reactor designs ex-vessel severe accident mitigation strategy employs a pool of water underneath the reactor vessel. If water pool is deep enough, the melt is expected to be fragmented and quenched and form a coolable debris bed preventing further accident progression. However, there is a possibility that upon contact with volatile coolant thermal energy stored in the hot melt will be converted into mechanical energy of rapidly expanding steam in the process of so called “steam explosion”. Energetics of the steam explosion is contingent upon conditions of melt release, pool characteristics and containment geometry. Containment failure due to the ex-vessel steam explosion can be a factor of risk for the “wet cavity” strategy if fragility limits are close to the expected loads. In order to assess the risk, we develop so called full model (based on TEXAS-V code) for the estimation of the steam explosion loads. To ensure model applicability to a wide range of LWR designs, a number of modifications have been introduced in comparison to previous works. A large database of Full Model solutions is used then for the development of a Surrogate Model based on the Artificial Neural Networks (ANN) to enable extensive sensitivity analysis and uncertainty quantification. The uncertainty in the SM approximation of the FM is considered explicitly in the assessment of failure probability. In this work, we demonstrate an approach to the validation of the Full Model against previous steam explosion experiments using a statistical approach in which a joint distribution of the experimental data is compared to a database of explosion distributions obtained using the full model.

Place, publisher, year, edition, pages
2019. p. 4568-4574
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-268322Scopus ID: 2-s2.0-85073726445OAI: oai:DiVA.org:kth-268322DiVA, id: diva2:1413392
Conference
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019; Marriott Portland Downtown WaterfrontPortland; United States; 18 August 2019 through 23 August 2019
Note

QC 20200310

Available from: 2020-03-10 Created: 2020-03-10 Last updated: 2020-03-10Bibliographically approved

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Scopushttps://nureth2018conference.wordpress.com/

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Grishchenko, DmitryKudinov, Pavel

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