Application of Lower Head Thermal-mechanical Creep Failure Module in LHF Experiment

  • Hao Yang
  • , Bin Zhang
  • , Pengcheng Gao
  • , Jianqiang Shan

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

Abstract

Under severe accident conditions, the core is melted due to insufficient cooling, and a large amount of molten material is relocated to the lower plenum of the Reactor Pressure Vessel (RPV), which may lead to the rupture of the lower head and radioactive release. As the second line of defense, the integrity of the lower head of the RPV plays an exceedingly significant role. Whether the lower head can ensure the retention of molten materials is of great significance to the safety analysis of the reactor. Therefore, in order to better evaluate the integrity of the lower head, it is necessary to mak e an in-depth analysis of the lower head. In this paper, the LHTCF (Lower Head Thermal-me chanical Creep Failure) module is developed based on the method of thermal-mechanical coup ling. Finally, the LHTCF module is integrated into the severe accident analysis program ISAA (Integrated Severe Accident Analysis) to simulate the LHF-1 (lower head failure, LHF) experiment. The numerical simulation results agree well with the experimental data. The findings reveal that the LHTCF model established in this paper can effectively predict the mechanical behavior of the lower head.

Original languageEnglish
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages4364-4379
Number of pages16
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: 20 Aug 202325 Aug 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period20/08/2325/08/23

Keywords

  • LHF-1 experiment
  • Lower head
  • Mechanical analysis
  • Severe accident

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