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Journal Articles

Prediction of critical heat flux for the forced convective boiling based on the mechanism

Ono, Ayako; Sakashita, Hiroto*; Yamashita, Susumu; Suzuki, Takayuki*; Yoshida, Hiroyuki

Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet), 7 Pages, 2022/10

The new prediction method of critical heat flux (CHF) of the fuel assemblies based on the mechanism is proposed in this study. The prediction method of CHF based on the mechanism has been needed for a long time to enhance the safety analysis and reduce the design cost. From several experimental findings of the liquid-vapor behavior near the heating surface from the nucleate boiling to the CHF, the authors consider that the macrolayer dryout model will be appropriate to predict the CHF under the reactor condition. The prediction method of the macrolayer thickness and the passage period of vapor mass in the fuel assemblies are needed to predict CHF from the macrolayer dryout model. In this study, the CHF under the forced convection is evaluated by combining the prediction methods for the macrolayer thickness and passage period of vapor mass, which are proposed by authors. The prediction of the CHF under the forced convection is examined and compared with the experimental data.

Journal Articles

Direct numerical simulation of turbulent heat transfer in plane impinging jet; Effects of impingement distance on heat transfer in confined space

Hattori, Hirofumi*; Sato, Hiroshi; Nagano, Yasutaka*

Nihon Kikai Gakkai Rombunshu, B, 70(696), p.1919 - 1926, 2004/08

no abstracts in English

Journal Articles

Heat transfer characteristics of gas heated type steam reformer

Takeda, Tetsuaki; Ohashi, Hirofumi; Inagaki, Yoshiyuki

Nihon Kikai Gakkai 2003-Nendo Nenji Taikai Koen Rombunshu, Vol.3, p.17 - 18, 2003/08

A technology development of a hydrogen production system by a nuclear heat are being performed as a heat application system of a high-temperature gas cooled reactor in the Japan Atomic Energy Research Institute. The objective of this study is to clarify heat transfer characteristics of the steam reformer in the HTTR hydrogen production system. An experiment has been performed using a double coaxial vertical tube to obtain the heat transfer characteristics and to evaluate the effectiveness of heat transfer enhancement. The amount of produced hydrogen increases with increasing not only reaction rate of catalysis but also the heat transfer coefficient. It is necessary to take into account of heat transfer from both surfaces of the double coaxial tube in order to obtain the amount of transferred heat from the heated tube to the coolant gas.

Journal Articles

Critical heat flux at high velocity channel flow with high subcooling

Sudo, Yukio; Kaminaga, Masanori

Nucl. Eng. Des., 187, p.215 - 227, 1999/00

 Times Cited Count:8 Percentile:52.64(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Critical heat flux of forced flow boiling in a narrow one-side heated rectangular flow channel

L.Zheng*; Iguchi, Tadashi; Kureta, Masatoshi; Akimoto, Hajime

JAERI-Research 97-054, 85 Pages, 1997/08

JAERI-Research-97-054.pdf:2.18MB

no abstracts in English

JAEA Reports

Numerical prediction of local transitional features of turbulent forced gas flows in circular tubes with strong heating

; A.M.Shehata*; Kunugi, Tomoaki; D.M.McEligot*

JAERI-Research 97-029, 36 Pages, 1997/03

JAERI-Research-97-029.pdf:1.61MB

no abstracts in English

Journal Articles

Experimental study on heat transfer characteristics of a high-temperature gas-gas heat exchanger with helically coiled tube bundles

Inagaki, Yoshiyuki; ; Ioka, Ikuo;

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART B), p.633 - 637, 1996/00

no abstracts in English

JAEA Reports

JAEA Reports

Thermal-hydraulic conceptual design of the multiple purpose research reactor MEX-15

M.A.Lucatero*; Kaminaga, Masanori

JAERI-M 94-006, 38 Pages, 1994/02

JAERI-M-94-006.pdf:1.27MB

no abstracts in English

Journal Articles

Thermal and hydraulic tests of a standard fuel rod of HTTR with HENDEL

Takase, Kazuyuki; Hino, Ryutaro;

Nihon Genshiryoku Gakkai-Shi, 32(11), p.1107 - 1110, 1990/11

 Times Cited Count:12 Percentile:86.08(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

Journal Articles

Combined forced and free convective heat transfer characteristics in narrow vertical rectangular channel heated from both sides

Sudo, Yukio; Kaminaga, Masanori;

Journal of Nuclear Science and Technology, 24(5), p.355 - 364, 1987/05

 Times Cited Count:7 Percentile:59.40(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Heat transfer by natural convection in a half-sphere heated from below

;

Journal of Nuclear Science and Technology, 23(6), p.568 - 570, 1986/00

 Times Cited Count:1 Percentile:27.82(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Core thermohydraulic design with 20% LEU fuel for upgraded research reactor,JRR-3

Sudo, Yukio; ; ;

Journal of Nuclear Science and Technology, 22(7), p.551 - 564, 1985/00

 Times Cited Count:22 Percentile:89.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of differences in single-phase forced-convection heat transfer characteristics between upflow and downflow for narrow rectangular channel

Sudo, Yukio; ; ; ; Kaminaga, Masanori

Journal of Nuclear Science and Technology, 22(3), p.202 - 212, 1985/00

 Times Cited Count:39 Percentile:95.28(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Annual Progress Report on the NSRR Experiments 14

;

JAERI-M 84-046, 176 Pages, 1984/03

JAERI-M-84-046.pdf:6.85MB

no abstracts in English

JAEA Reports

Semiannual Progress Report on the NSRR Experiments(13)

;

JAERI-M 83-193, 112 Pages, 1983/11

JAERI-M-83-193.pdf:4.31MB

no abstracts in English

JAEA Reports

Semiannual Progress Report on the NSRR Experiments (12)

;

JAERI-M 82-012, 122 Pages, 1982/03

JAERI-M-82-012.pdf:5.69MB

no abstracts in English

25 (Records 1-20 displayed on this page)