Critical heat flux prediction for subcooled flow boiling in annulus

Liu, W.

Dai-20-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.391 - 392, 2015/06

Subcooled flow boiling is a boiling that begins and develops even though the mean enthalpy of liquid phase is lower than saturation. This forced convective boiling is one of the most efficient ways for the removal of high heat flux. It is widely used in the high heat flux components such as nuclear reactor cores, accelerator targets and fusion reactor components. The thermal outputs of these systems are restricted by Critical Heat Flux(CHF). Because of the importance of the CHF, lots of researches, including both experimental and mechanistic modelling, have been performed. However, the CHF prediction for rod bundles still remains unsolved. As the first step for the CHF prediction in rod bundles, in this paper, we tried to predict the CHF in annulus, which is the most basic flow geometry simplified from a rod bundle. We performed the CHF prediction by using liquid sublayer dryout model, combined with Nouri single phase velocity distribution correlation for annulus. The results show that the CHF in annulus can be predicted in an accuracy of about 20%.

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

Kureta, Masatoshi; Akimoto, Hajime; Hibiki, Takashi*; Mishima, Kaichiro*

Nuclear Technology, 136(2), p.241 - 254, 2001/11

https://doi.org/10.13182/NT01-A3242

no abstracts in English

Measurement of boiling flow by high-frame-rate neutron radiography, 2; Point of net vapor generation of flow-boiling in rectangular channels with short heated length

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

Nihon Kikai Gakkai Rombunshu, B, 67(661), p.2295 - 2303, 2001/09

https://doi.org/10.1299/kikaib.67.2295

no abstracts in English

Study on subcooled-boiling flow in short-heated-length rectangular channels; Measurement of instantaneous void fraction using neutron radiography technique

Kureta, Masatoshi; Akimoto, Hajime

Konsoryu Shimpojiumu 2000 (Dai-19-Kai) Koen Rombunshu, p.59 - 60, 2000/00

no abstracts in English

Development of measruement method of void fraction distribution on subcooled flow boiling using neutron radiography

Kureta, Masatoshi; Matsubayashi, Masahito; Akimoto, Hajime

JAERI-Research 99-023, 29 Pages, 1999/03

JAERI-Research-99-023.pdf:1.67MB

no abstracts in English

Visualization and void fraction measurement of subcooled boiling water flow in a narrow rectangular channel using high-frame-rate neutron radiography

Kureta, Masatoshi; Hibiki, Takashi*; Mishima, Kaichiro*; Akimoto, Hajime

Two-Phase Flow Modelling and Experimentation 1999, p.1509 - 1514, 1999/00

no abstracts in English

Analysis of the JAERI critical heat flux data base for fusion application

J.Boscary*; Araki, Masanori; Akiba, Masato

JAERI-Research 97-053, 50 Pages, 1997/08

JAERI-Research-97-053.pdf:1.71MB

no abstracts in English