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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:35.25(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.

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

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

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

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:40.89(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

JAEA Reports

FREG-1; A Computer Program for Calculating the Gap Conductance in Oxide Fuel Pins

; ; ; ; ; ; *

JAERI-M 5958, 51 Pages, 1975/01

JAERI-M-5958.pdf:1.45MB

no abstracts in English

JAEA Reports

A Comentary on the GAPCON-THERMAL-1

; ; ; ; ; ; *

JAERI-M 5728, 102 Pages, 1974/06

JAERI-M-5728.pdf:3.45MB

no abstracts in English

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