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Journal Articles

Conductance of a long rectangular channel; Pressure dependence

Ogiwara, Norio; Hikichi, Yusuke*; Kamiya, Junichiro; Kinsho, Michikazu; Yoshida, Hajime*; Arai, Kenta*

Journal of the Vacuum Society of Japan, 60(12), p.475 - 480, 2017/12

Journal Articles

Analysis on lift-off experiment in Halden reactor by FEMAXI-6 code

Suzuki, Motoe; Kusagaya, Kazuyuki*; Saito, Hiroaki*; Fuketa, Toyoshi

Journal of Nuclear Materials, 335(3), p.417 - 424, 2004/12

 Times Cited Count:5 Percentile:35.2(Materials Science, Multidisciplinary)

Experimental analysis was conducted on the Lift-Off experiment IFA-610.1 in Halden reactor by the FEMAXI-6 code using the detailed measured conditions of test-irradiation. Calculated fuel center temperatures on the two assumptions, i.e., (1) an enhanced thermal conductance across the pellet-clad bonding layer is maintained during the cladding creep-out by over-pressurization, and (2) the bonding layer is broken by the cladding creep-out, were compared with the measured data to analyze the effect of the creep-out by over-pressure inside the test pin. The measured center temperature rise was higher by a few tens of K than the prediction performed on the assumption (1), though this difference was much smaller than the predicted rise on the assumption (2). Therefore, it is appropriate to attribute the measured center temperature rise to the decrease of effective thermal conductance by irregular re-location of pellet fragments, etc. which was caused by cladding creep-out.

Journal Articles

Experimental study on thermal-hydraulics and neutronics coupling effect on flow instability in a heated channel with THYNC facility

Iguchi, Tadashi; Shibamoto, Yasuteru; Asaka, Hideaki; Nakamura, Hideo

Proceedings of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), 16 Pages, 2003/10

Thermal-hydraulic and neutronic dynamics are always interrelated in BWR core. This is called thermal-hydraulic and neutronic (T/N) coupling. Channel stability experiments with T/N coupling under non-nuclear condition are very limited. This is mainly due to the difficulties in the real-time simulation of neutron dynamics and in the fast-response void fraction measurement under high-pressure and temperature conditions. Authors have developed techniques to solve the above difficulties, and have succeeded in experimentally simulating T/N coupling under non-nuclear conditions with the THYNC facility. Using THYNC facility, T/N coupling effect on channel stability was investigated. Experiments were performed under Pressure=2-7MPa, Subcooling=10-40K, and Mass flux=270-660kg/m$$^{2}$$s. THYNC results indicated T/N coupling lowered the channel stability threshold. The reduction of channel stability threshold due to T/N coupling was small within 10% at 7MPa in the present THYNC experiment, although the experimental condition was set to be more severe than that supposed in a reactor.

JAEA Reports

Development of quick-response area-averaged void fraction meter; Application to BWR condition

Iguchi, Tadashi; Watanabe, Hironori; Kimura, Mamoru*; Anoda, Yoshinari

JAERI-Research 2001-032, 111 Pages, 2001/05

JAERI-Research-2001-032.pdf:4.14MB

no abstracts in English

JAEA Reports

Comparison of heat capacity and thermal time constant between BWR fuel and simulated heater rod

Iguchi, Tadashi

JAERI-Research 2000-050, 107 Pages, 2000/09

JAERI-Research-2000-050.pdf:4.29MB

no abstracts in English

JAEA Reports

Light water reactor fuel analysis code FEMAXI-V(Ver.1)

Suzuki, Motoe

JAERI-Data/Code 2000-030, 280 Pages, 2000/09

JAERI-Data-Code-2000-030.pdf:11.06MB

no abstracts in English

JAEA Reports

Development of heat conduction type cesium injection device for negative-ion source for JT-60U

*; Ito, Takao; Usui, Katsutomi; Mogaki, Kazuhiko; Kuriyama, Masaaki; Sato, Fujio*; Oshima, Katsumi*; Omori, Kenichiro; Watanabe, Kazuhiro

JAERI-Tech 99-054, 49 Pages, 1999/07

JAERI-Tech-99-054.pdf:1.92MB

no abstracts in English

JAEA Reports

Light water reactor fuel analysis code FEMAXI-IV, 2; Detailed structure and user's manual

Suzuki, Motoe; Saito, Hioraki*

JAERI-Data/Code 97-043, 235 Pages, 1997/11

JAERI-Data-Code-97-043.pdf:5.84MB

no abstracts in English

Journal Articles

Electrical circuit models among superconducting strands in real-scale CICCs

*; *; Fujioka, T.*; *; Koizumi, Norikiyo; Ando, Toshinari; Tsuji, Hiroshi

IEEE Transactions on Applied Superconductivity, 7(2), p.215 - 218, 1997/06

 Times Cited Count:5 Percentile:45.49(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Feasibility study on the applicability of a diffusion-welded compact intermediate heat exchanger to next-generation high temperature gas-cooled reactor

Takeda, Takeshi; Kunitomi, Kazuhiko; *; *

Nucl. Eng. Des., 168, p.11 - 21, 1997/00

 Times Cited Count:46 Percentile:93.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effect of eccentric pellet on gap conductance in fuel rod

; ; Hoshiya, Taiji

Journal of Nuclear Science and Technology, 28(10), p.961 - 964, 1991/10

no abstracts in English

JAEA Reports

JAEA Reports

A Fundamental characteristic of V.C.H.P. for JMTR capsule

Tsuyuzaki, Noriyoshi; Saito, Takashi; *

JAERI-M 88-227, 12 Pages, 1988/11

JAERI-M-88-227.pdf:0.45MB

no abstracts in English

JAEA Reports

Evaluation of parameters effect on the maximum fuel temperature in the core thermal hydraulic design of HTTR

Fujimoto, Nozomu; Maruyama, So; Fujii, Sadao*; Niguma, Yoshinoro*; Sudo, Yukio

JAERI-M 88-187, 79 Pages, 1988/10

JAERI-M-88-187.pdf:1.65MB

no abstracts in English

Journal Articles

Analytical study of thermal response similarity between simulated fuel rods and nuclear fuel rods during reflood phase of PWR-LOCA

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 23(4), p.315 - 325, 1986/00

 Times Cited Count:3 Percentile:40.87(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Journal Articles

JAEA Reports

A LOCA Analysis of BWR/6 for the ROSA-III Test

*; ;

JAERI-M 8185, 120 Pages, 1979/03

JAERI-M-8185.pdf:2.47MB

no abstracts in English

24 (Records 1-20 displayed on this page)