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Liu, W.; Podowski, M. Z.*
Nihon Kikai Gakkai Netsu Kogaku Konfuarensu 2015 Koen Rombunshu (CD-ROM), 2 Pages, 2015/10
This paper gives prediction to the transient heat transfer at Departure of Nucleate Boiling (DNB) point for subcooled flow boiling. The prediction is carried out by solving the heat conduction equations in cylindrical coordinates with convective boundary condition, which changes with the change of the heat transfer mode on the heated surface. DNB is assumed to happen at the complete dryout of liquid sublayer trapped between the heated wall and an elongated vapor clot, during the passing time of the vapor clot. Important parameters including initial thickness of the liquid sublayer, vapor clot length, vapor clot velocity and void fraction etc., are calculated from the Liu - Nariai model. The initial heater surface temperature is derived from the Jens-Lottes correlation. The transient changes of liquid sublayer thickness, surface temperature at DNB are reported. No obvious temperature jumping is observed at DNB. To predict temperate excursion at Critical Heat Flux (CHF), more simulations to the transient boiling and film boiling processes are needed.
Takamatsu, Kuniyoshi; Furusawa, Takayuki; Hamamoto, Shimpei; Nakagawa, Shigeaki
Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 11 Pages, 2004/10
Safety demonstration tests using the High Temperature Engineering Test Reactor (HTTR) are in progress to verify the inherent safety features for High Temperature Gas-cooled Reactors (HTGRs). The coolant flow reduction test by tripping one or two out of three gas circulators is one of the safety demonstration tests. The reactor power safely brings to a stable level without a reactor scram and the temperature transient of the reactor-core is very slow. Through the safety demonstration test, the two dimensional temperature analysis code (TAC-NC code) was improved. This paper describes the validation of the TAC-NC code using the measured value of the test by tripping of one and two out of three gas circulators at 30%(9MW). The TAC-NC code could evaluate accurately the temperature transient within 10% during the test. Also, it was confirmed that the temperature transient by tripping all gas circulators is very slow.
S.Navarro-Valenti*; S.H.Kim*; V.Georgevich*; R.P.Taleyarkhan*; Fuketa, Toyoshi; Soyama, Kazuhiko; Ishijima, Kiyomi; Kodaira, Tsuneo
NUREG/CP-0142 (Vol. 4), 0, p.2957 - 2976, 1996/00
no abstracts in English
Iwamura, Takamichi; Watanabe, Hironori; Araya, Fumimasa; Okubo, Tsutomu; Murao, Yoshio
JAERI-M 92-050, 46 Pages, 1992/03
no abstracts in English
JAERI-M 84-063, 166 Pages, 1984/03
no abstracts in English
;
Nucl.Eng.Des., 73(3), p.253 - 263, 1983/00
Times Cited Count：1 Percentile：21.55(Nuclear Science & Technology)no abstracts in English
Tasaka, Kanji; ; ; ; ; C.P.Fineman*; D.R.Bosley*;
JAERI-M 9849, 67 Pages, 1981/12
no abstracts in English
;
JAERI-M 8047, 106 Pages, 1979/01
no abstracts in English
;
JAERI-M 7808, 173 Pages, 1978/08
no abstracts in English
;
JAERI-M 7489, 84 Pages, 1978/01
no abstracts in English
;
JAERI-M 7396, 61 Pages, 1977/11
no abstracts in English
; ; ; ; ; ; ; ; ; ; et al.
JAERI-M 6318, 157 Pages, 1975/11
no abstracts in English
