American Nuclear Society
Home

Home / Store / Journals / Electronic Articles / Nuclear Technology / Volume 136 / Number 2 / Pages 241-254

Void Fraction Measurement in Subcooled-Boiling Flow Using High-Frame-Rate Neutron Radiography

Masatoshi Kureta, Hajime Akimoto, Takashi Hibiki, Kaichiro Mishima

Nuclear Technology / Volume 136 / Number 2 / Pages 241-254

November 2001

Format:

Price:$30.00
Member Price:$27.00
Member Savings:$3.00

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/(m2s). 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.

 
 
 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement