Experimental study of droplet sizes across a spacer grid location under various reflood conditions

Yue Jin, Faith Beck, Brian R. Lowery, Douglas J. Miller, Fan-bill B. Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie

Research output: Contribution to journalArticle

7 Citations (Scopus)

Abstract

Droplet size and distribution across a spacer grid in a heated rod bundle during reflood stage of a postulated design basis accident loss of coolant accident (LOCA) are studied experimentally using the Rod Bundle Heat Transfer (RBHT) test facility. Effects of spacer grid conditions, quench front location during reflood, and inlet water subcooling on droplet field are investigated. Experimental results show that the droplet sizes decrease when they pass through a dry spacer grid due to cutting and shattering effects at the lower edges of the spacer grid. On the other hand, for a wet grid, the droplet sizes downstream of the grid could be larger than those at the upstream locations, as the droplet generation mechanism, for a wet grid, is due to the formation of liquid ligaments at the trailing edge of the spacer grid and the subsequent aerodynamic breakup of these ligaments into relatively larger droplets induced by instabilities. It is found that, as the quench front propagates upward, sizes of incoming droplets increase correspondingly as a result of the droplet-vapor thermal-hydraulic interactions along the flow channels. The experimental results also indicate that larger droplet diameters occur when the inlet water subcooling is higher. Results of the present study can be utilized to develop models for droplet field behavior under accident scenarios. These models can be incorporated into nuclear reactor thermal-hydraulic safety analysis codes such as COBRA-TF and TRACE.

Original languageEnglish (US)
Pages (from-to)246-257
Number of pages12
JournalExperimental Thermal and Fluid Science
Volume94
DOIs
StatePublished - Jun 1 2018

Fingerprint

Ligaments
Accidents
Hydraulics
Loss of coolant accidents
Water
Channel flow
Nuclear reactors
Test facilities
Aerodynamics
Vapors
Heat transfer
Liquids
Hot Temperature

All Science Journal Classification (ASJC) codes

  • Chemical Engineering(all)
  • Nuclear Energy and Engineering
  • Aerospace Engineering
  • Mechanical Engineering
  • Fluid Flow and Transfer Processes

Cite this

Jin, Yue ; Beck, Faith ; Lowery, Brian R. ; Miller, Douglas J. ; Cheung, Fan-bill B. ; Bajorek, Stephen M. ; Tien, Kirk ; Hoxie, Chris L. / Experimental study of droplet sizes across a spacer grid location under various reflood conditions. In: Experimental Thermal and Fluid Science. 2018 ; Vol. 94. pp. 246-257.
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abstract = "Droplet size and distribution across a spacer grid in a heated rod bundle during reflood stage of a postulated design basis accident loss of coolant accident (LOCA) are studied experimentally using the Rod Bundle Heat Transfer (RBHT) test facility. Effects of spacer grid conditions, quench front location during reflood, and inlet water subcooling on droplet field are investigated. Experimental results show that the droplet sizes decrease when they pass through a dry spacer grid due to cutting and shattering effects at the lower edges of the spacer grid. On the other hand, for a wet grid, the droplet sizes downstream of the grid could be larger than those at the upstream locations, as the droplet generation mechanism, for a wet grid, is due to the formation of liquid ligaments at the trailing edge of the spacer grid and the subsequent aerodynamic breakup of these ligaments into relatively larger droplets induced by instabilities. It is found that, as the quench front propagates upward, sizes of incoming droplets increase correspondingly as a result of the droplet-vapor thermal-hydraulic interactions along the flow channels. The experimental results also indicate that larger droplet diameters occur when the inlet water subcooling is higher. Results of the present study can be utilized to develop models for droplet field behavior under accident scenarios. These models can be incorporated into nuclear reactor thermal-hydraulic safety analysis codes such as COBRA-TF and TRACE.",
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Experimental study of droplet sizes across a spacer grid location under various reflood conditions. / Jin, Yue; Beck, Faith; Lowery, Brian R.; Miller, Douglas J.; Cheung, Fan-bill B.; Bajorek, Stephen M.; Tien, Kirk; Hoxie, Chris L.

In: Experimental Thermal and Fluid Science, Vol. 94, 01.06.2018, p. 246-257.

Research output: Contribution to journalArticle

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AU - Jin, Yue

AU - Beck, Faith

AU - Lowery, Brian R.

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AU - Tien, Kirk

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