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Journal Articles

Critical heat flux prediction for subcooled flow boiling in annulus

Liu, W.; Podowski, M. Z.*

Nihon Kikai Gakkai Netsu Kogaku Konfarensu 2016 Koen Rombunshu (USB Flash Drive), 2 Pages, 2016/10

Prediction of Critical Heat Flux (CHF) is important for nuclear reactor safety. However, the CHF prediction for subcooled flow boiling in complicated geometry such as fuel assembly 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 fuel bundle. We performed the CHF prediction by using liquid sublayer dryout model, combining with ANSYS CFX code to get the single phase velocity distribution inside the annulus. The results show that the CHF in annulus can be predicted in an accuracy of about $$pm$$20%.

Journal Articles

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 $$pm$$20%.

Journal Articles

Present status of HTTR program

Mogi, Haruyoshi; Tanaka, Toshiyuki; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru

Doryoku, Enerugi Gijutsu No Saizensen : Shimpojiumu Koen Rombunshu 1994, 0, p.305 - 310, 1994/00

no abstracts in English

JAEA Reports

Safety analysis on pipe rupture accidents in primary cooling system for HTTR

Maruyama, So; *; Nakagawa, Shigeaki; Shindo, Masami

JAERI-M 90-195, 33 Pages, 1990/10

JAERI-M-90-195.pdf:0.87MB

no abstracts in English

Journal Articles

Radiation-induced decomposition of phenol in flow system

; ; Kawakami, Waichiro

Radiation Physics and Chemistry, (1), p.59 - 65, 1980/00

no abstracts in English

Journal Articles

Decoloration and degradation of an anthraquinone dye aqueous solution in flow system using an electron accelerator

; *; ; Kawakami, Waichiro

Radiation Physics and Chemistry, 13(3-4), p.107 - 113, 1979/00

no abstracts in English

Journal Articles

Electron-beam oxidation treatment of a commercial dye by use of a dual-tube bubbling column reactor

Kawakami, Waichiro; ; ; ;

Environmental Science & Technology, 12(2), p.189 - 194, 1978/02

 Times Cited Count:17

no abstracts in English

Journal Articles

Analysis of transient heat transfer for turbulent flow in onnuli, 1

Nihon Kikai Gakkai Rombunshu, B, 39(324), p.2498 - 2511, 1973/00

no abstracts in English

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