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Thermo-mechanical analysis of instrumentation guide tube failure during a severe accident in a nordic boiling water reactor
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0003-3132-7252
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
2020 (English)In: International Conference on Nuclear Engineering, Proceedings, ICONE 2020, ASME Press, 2020, Vol. 1, article id V001T01A003Conference paper, Published paper (Refereed)
Abstract [en]

Vessel penetrations are important features of both pressurized water reactors and boiling water reactors. The thermal and structural behaviour of instrumentation guide tubes (IGTs) and control rod guide tubes (CRGTs) during a severe accident is vital in the assessment of the structure integrity of the reactor pressure vessel. Penetrations may fail due to welding failure, nozzle rupture, melt-through, etc. It is thus important to assess the failure mechanisms of penetrations with sufficient details. The objective of this paper is to assess the timing and failure modes of IGTs at the lower head during a severe accident in a Nordic boiling water reactor. In this study, a three-dimensional local finite element model was established using Ansys Mechanical that includes the vessel wall, the nozzle, and the weld joint. The thermo-mechanical loads of the finite element model were based on MELCOR results of a station blackout accident (SBO) combined with a large-break loss-of-coolant accident (LBLOCA) including an external vessel cooling by water as a severe accident management strategy. Given the temperature, creep strain, elastic strain, plastic strain, stress and displacement from the ANSYS simulations, the results showed the timing and failure modes of IGTs. Failure of the IGT penetration by nozzle creep is found to be the dominant failure mode of the vessel. However, it was also found that the IGT is clamped by the flow limiter before the nozzle creep, which means that IGT ejection is unlikely.

Place, publisher, year, edition, pages
ASME Press, 2020. Vol. 1, article id V001T01A003
Keywords [en]
Failure mode, Instrumentation guide tube, Severe accident, Timing, Boiling water reactors, Computational fluid dynamics, Creep, Failure modes, Finite element method, Loss of coolant accidents, Nozzles, Nuclear engineering, Nuclear fuels, Outages, Pressure vessels, Pressurized water reactors, Reactor cores, Two phase flow, Welding codes, Welds, Control rod guide tubes, Large break loss of coolant accidents, Reactor Pressure Vessel, Severe accident management, Stress and displacements, Structural behaviour, Thermo mechanical loads, Thermo-mechanical analysis, Failure (mechanical)
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-290409DOI: 10.1115/ICONE2020-16236ISI: 000850727000003Scopus ID: 2-s2.0-85095768882OAI: oai:DiVA.org:kth-290409DiVA, id: diva2:1532579
Conference
2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference, Virtual/Online, 4 April - 5 April 2020
Note

Part of ISBN 978-488898256-6

QC 20230921

Available from: 2021-03-02 Created: 2021-03-02 Last updated: 2023-09-21Bibliographically approved

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Yue, YingVillanueva, WalterWang, Hongdi

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