Void fraction measurement in subcooled-boiling flow using high-frame-rate neutron radiography

Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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Author(s)

Detail(s)

Original languageEnglish
Pages (from-to)241-254
Journal / PublicationNuclear Technology
Volume136
Issue number2
Publication statusPublished - 2001
Externally publishedYes

Abstract

A high-frame-rate neutron radiography (NR) technique was applied to measure the void fraction distribution in forced-convective subcooled-boiling flow. The focus was experimental technique and error estimation of the high-frame-rate NR. The results of void fraction measurement in the boiling flow were described. Measurement errors on instantaneous and time-averaged void fractions were evaluated experimentally and analytically. Measurement errors were within 18 and 2% for instantaneous void fraction (measurement time is 0.89 ms), and time-averaged void fraction, respectively. The void fraction distribution of subcooled boiling was measured using atmospheric-pressure water in rectangular channels with channel width 30 mm, heated length 100 mm, channel gap 3 and 5 mm, inlet water subcooling from 10 to 30 K, and mass velocity ranging from 240 to 2000 kg/(m2·s). One side of the channel was heated homogeneously. Instantaneous void fraction and time-averaged void fraction distribution were measured parametrically. The effects of flow parameters on void fraction were investigated.

Research Area(s)

  • Measurement, Neutron radiography, Void fraction

Bibliographic Note

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Citation Format(s)

Void fraction measurement in subcooled-boiling flow using high-frame-rate neutron radiography. / Kureta, M.; Akimoto, H.; Hibiki, T. et al.
In: Nuclear Technology, Vol. 136, No. 2, 2001, p. 241-254.

Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review