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Journal Articles

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 1; Overview of IVR evaluation in Anticipated Transient without Scram (ATWS)

Suzuki, Toru; Sogabe, Joji; Tobita, Yoshiharu; Sakai, Takaaki*; Nakai, Ryodai

Nihon Kikai Gakkai Rombunshu (Internet), 83(848), p.16-00395_1 - 16-00395_9, 2017/04

no abstracts in English

Journal Articles

Prediction of heater surface temperature change at subcooled flow boiling DNB

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.

Journal Articles

Feasibility study of BWR-type reduced-moderation water reactor core design in thermal-hydraulic view point

Araya, Fumimasa; Kureta, Masatoshi; Akimoto, Hajime

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.309 - 314, 2000/00

no abstracts in English

Journal Articles

A Preliminary experiment for a loss of vacuum events of fusion reactors

Takase, Kazuyuki; Kunugi, Tomoaki; Shibata, Mitsuhiko; Seki, Yasushi

Nihon Genshiryoku Gakkai-Shi, 38(11), p.904 - 906, 1996/00

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Transient analysis for design of primary coolant pump adopted to JAERI passive safety reactor JPSR

Araya, Fumimasa; Murao, Yoshio; Iwamura, Takamichi

Journal of Nuclear Science and Technology, 32(10), p.1039 - 1046, 1995/10

 Times Cited Count:5 Percentile:49.19(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Conceptual design of the JAERI passive safety reactor and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

Transactions of the American Nuclear Society, 71, p.527 - 529, 1995/00

no abstracts in English

Journal Articles

Conceptual design of JAERI passive safety reactor (JPSR) and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

10th Proc. of Nuclear Thermal Hydraulics, 0, p.3 - 12, 1994/00

no abstracts in English

JAEA Reports

Accident simulation tests for high conversion light water reactor using a high pressure water loop

Iwamura, Takamichi; Watanabe, Hironori; Araya, Fumimasa; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 92-050, 46 Pages, 1992/03

JAERI-M-92-050.pdf:1.24MB

no abstracts in English

Journal Articles

Application of a vibrating-vane type sensor to transient void measurements in nuclear reactor in-vessel environments

; Fuketa, Toyoshi;

Proc. of the Int. Conf. on Multiphase Flows 91-TSUKUBA,Vol. 2, p.247 - 250, 1991/00

no abstracts in English

JAEA Reports

Critical heat flux experiments for high conversion light water reactor, 3; Heated length: 0.5$$sim$$1.0m, P/D: 1.126$$sim$$1.2, number of rods: 4$$sim$$7

Iwamura, Takamichi; Okubo, Tsutomu; ; ; Murao, Yoshio

JAERI-M 90-044, 158 Pages, 1990/03

JAERI-M-90-044.pdf:2.81MB

no abstracts in English

Journal Articles

Transient burnout under rapid flow reduction condition

Journal of Nuclear Science and Technology, 24(10), p.811 - 820, 1987/10

 Times Cited Count:4 Percentile:44.68(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study of Transient Burnout under Flow Reduction Condition

JAERI-M 86-135, 89 Pages, 1986/09

JAERI-M-86-135.pdf:2.43MB

no abstracts in English

Journal Articles

Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3

Hirano, Masashi; Sudo, Yukio

Journal of Nuclear Science and Technology, 23(4), p.352 - 368, 1986/00

 Times Cited Count:20 Percentile:86.64(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of transient two-phase flow analyzer:MINCS

; Hirano, Masashi; ; ; ; ;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 72, 1986/00

no abstracts in English

JAEA Reports

Study of Transient Burnout Characteristics under Flow Reduction Condition

;

JAERI 1290, 42 Pages, 1984/03

JAERI-1290.pdf:2.2MB

no abstracts in English

Journal Articles

Burnout characteristics under flow reduction condition

;

Journal of Nuclear Science and Technology, 19(6), p.438 - 448, 1982/00

 Times Cited Count:9 Percentile:68.57(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Conceptual Design of Large Scale Test Facility(LSTF) of ROSA-IV Program for PWR Small Break LOCA Integral Experiment

Tasaka, Kanji; ; ; ; ; C.P.Fineman*; D.R.Bosley*;

JAERI-M 9849, 67 Pages, 1981/12

JAERI-M-9849.pdf:1.58MB

no abstracts in English

JAEA Reports

Flow Reduction Transient Burnout in a Vertical Tube,1

;

JAERI-M 8774, 138 Pages, 1980/03

JAERI-M-8774.pdf:3.38MB

no abstracts in English

Journal Articles

Transient behaviors of gas in thermal insulation media at rapid depressurization

; ; Okamoto, Yoshizo; ;

Journal of Nuclear Science and Technology, 16(10), p.732 - 740, 1979/10

 Times Cited Count:1

no abstracts in English

22 (Records 1-20 displayed on this page)