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Journal Articles

FEMAXI-IV: A Computer code for the analysis of thermal and mechanical behavior of light water fuel rods

; Saito, Hioraki*; *

Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. C, p.1 - 6, 1991/08

no abstracts in English

Journal Articles

Irradiation studies of JAERIs fuel at Halden reactor

Ichikawa, Michio; Uchida, Masaaki; Yanagisawa, Kazuaki; Nakamura, Jinichi;

Journal of Nuclear Science and Technology, 25(8), p.609 - 614, 1988/08

 Times Cited Count:2 Percentile:37.29(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of fuel behavior in power-ramp tests by FEMAXI-IV code

; Ki-S.Sim*

Res Mech., 25, p.101 - 128, 1988/00

no abstracts in English

Journal Articles

A Comparison between fission gas release data and FEMAXI-IV code calculations

; *

Nucl.Eng.Des., 101, p.267 - 279, 1987/00

 Times Cited Count:25 Percentile:89.23(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

FEMAXI-III :A computer code for the analysis of thermal and mechanical behavior of fuel rods

; Ichikawa, Michio; *; *; *; *; *; *

JAERI 1298, 90 Pages, 1985/12

JAERI-1298.pdf:3.59MB

no abstracts in English

Journal Articles

FEMAXI-IV:A computer code for the analysis of fuel rod behavior under transient condition

Nucl.Eng.Des., 88, p.69 - 84, 1985/00

 Times Cited Count:7 Percentile:68.44(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

FEMAXI-III; An Axisymmetric Finite Element Fuel Behaviour Code

; Ichikawa, Michio; *; *; *; *; *; *

JAERI-M 9251, 64 Pages, 1981/01

JAERI-M-9251.pdf:1.35MB

no abstracts in English

JAEA Reports

JAEA Reports

Oral presentation

Evaluation of Doppler reactivity effect in MOX fueled LWR using FCA, 2; Analysis of experimental data of UO$$_{2}$$ samples in a uranium fueled core

Suzuki, Motomu*; Yamamoto, Toru*; Ando, Yoshihira*; Nakajima, Tetsuo*; Ando, Masaki; Kugo, Teruhiko; Okajima, Shigeaki

no journal, , 

To obtain experimental data to evaluate calculation accuracy for the Doppler effect in MOX fueled LWR, a series of experiment has been carried out at FCA with the use of uranium and plutonium samples. Parametric survey calculations as for the modeling, nuclear data library and calculation method were carried out for the experiments in the uranium core using uranium samples. The effect of those parameters for the calculation of the Doppler effect was obtained.

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