Large-break LOCA analysis with modified boiling heat-transfer model in TRACE code

Riichiro Okawa, Masahiro Furuya

Research output: Contribution to journalArticle

Abstract

Numerical analyses were conducted to replicate several tests for simulating a double-ended cold-leg large break loss-of-coolant accident (LBLOCA) in the Loss-of-Fluid Test (LOFT) using the TRACE (version 5/patch level 4) code. Analytical results by the original TRACE code were so conservative that especially a first peak of cladding temperature was estimated higher than the experimental data at the blowdown phase and subsequent temperature drop corresponding to the temporal quench was not seen. We were interested in minimum film boiling temperature (T min ) as a heat transfer model factor estimating the quench at the moment, investigated correlation equations for T min in previous studies and especially focused on ones given as a function of coolant mass flow because the complicated flow transient and decompression in the core region at the blowdown phase was interpreted as having an influence on the cladding temperature behavior. There are several correlations meeting the above condition but it was revealed that they are insufficient to apply for high pressure especially. Therefore, a new term including an effect of mass flow flux and time derivative of pressure was defined and added with a proportional coefficient hypothetically to the current correlation in the TRACE code for modification. The LOFT analyses were conducted again using the modified TRACE code, and it was shown by applying roughly the same proportional coefficient to all the cases of LOFT analyses that estimation of the cladding temperature behavior was improved more precisely at the blowdown phase. Also, the transition during the phase was explained phenomenologically with the wall heat transfer mode and boiling curve.

Original languageEnglish
Pages (from-to)97-111
Number of pages15
JournalNuclear Engineering and Design
Volume346
DOIs
Publication statusPublished - 2019 May 1
Externally publishedYes

Fingerprint

Loss of coolant accidents
boiling
Boiling liquids
heat transfer
Heat transfer
mass flow
temperature
Fluids
fluid
fluids
Temperature
loss of coolant
film boiling
transient flow
pressure reduction
coolants
coefficients
decompression
accidents
Coolants

Keywords

  • Boiling heat transfer
  • LOCA
  • LOFT
  • Minimum film boiling temperature
  • PCT
  • TRACE

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

Cite this

Large-break LOCA analysis with modified boiling heat-transfer model in TRACE code. / Okawa, Riichiro; Furuya, Masahiro.

In: Nuclear Engineering and Design, Vol. 346, 01.05.2019, p. 97-111.

Research output: Contribution to journalArticle

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