Scaling of quench front and entrainment-related phenomena

M. J. Holowach, L. E. Hochreiter, F. B. Cheung, D. L. Aumiller, R. J. Houser

Research output: Contribution to journalArticle

1 Citation (Scopus)

Abstract

The scaling of thermal hydraulic systems is of great importance in the development of experiments in laboratory-scale test facilities that are used to replicate the response of full-size prototypical designs. One particular process that is of interest in experimental modeling is the quench front that develops during the reflood phase in a pressurized water reactor (PWR) following a large-break loss of coolant accident (LOCA). The purpose of this study is to develop a scaling methodology such that the prototypical quench front related phenomena such as the entrainment of liquid droplets can be preserved in a laboratory-scale test facility which may have material, geometrical, fluid, and flow differences as compared to the prototypical case. A mass and energy balance on a Lagrangian quench front control volume along with temporal scaling methods are utilized in developing the quench front scaling groups for a phenomena-specific second-tier scaling analysis. A sample calculation is presented comparing the quench front scaling groups calculated for a prototypical Westinghouse 17 × 17 PWR fuel design and that of the geometry and material configuration used in the FLECHT-SEASET series of experiments.

Original languageEnglish (US)
Pages (from-to)197-209
Number of pages13
JournalNuclear Engineering and Design
Volume223
Issue number2
DOIs
StatePublished - Aug 1 2003

Fingerprint

Pressurized water reactors
entrainment
Test facilities
scaling
Loss of coolant accidents
Energy balance
pressurized water reactors
Experiments
Hydraulics
test facilities
Fluids
Geometry
Liquids
loss of coolant
hydraulic equipment
nuclear fuels
mass balance
energy balance
droplet
accident

All Science Journal Classification (ASJC) codes

  • 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

Holowach, M. J., Hochreiter, L. E., Cheung, F. B., Aumiller, D. L., & Houser, R. J. (2003). Scaling of quench front and entrainment-related phenomena. Nuclear Engineering and Design, 223(2), 197-209. https://doi.org/10.1016/S0029-5493(03)00043-8
Holowach, M. J. ; Hochreiter, L. E. ; Cheung, F. B. ; Aumiller, D. L. ; Houser, R. J. / Scaling of quench front and entrainment-related phenomena. In: Nuclear Engineering and Design. 2003 ; Vol. 223, No. 2. pp. 197-209.
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Holowach, MJ, Hochreiter, LE, Cheung, FB, Aumiller, DL & Houser, RJ 2003, 'Scaling of quench front and entrainment-related phenomena', Nuclear Engineering and Design, vol. 223, no. 2, pp. 197-209. https://doi.org/10.1016/S0029-5493(03)00043-8

Scaling of quench front and entrainment-related phenomena. / Holowach, M. J.; Hochreiter, L. E.; Cheung, F. B.; Aumiller, D. L.; Houser, R. J.

In: Nuclear Engineering and Design, Vol. 223, No. 2, 01.08.2003, p. 197-209.

Research output: Contribution to journalArticle

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