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Kojima, Takuji
Hoshasen Kagaku, 2001(72), p.37 - 40, 2001/08
no abstracts in English
Ishikawa, Nobuyuki; Suzuki, Katsuo
Nihon Genshiryoku Gakkai-Shi, 41(9), p.937 - 945, 1999/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Ishikawa, Nobuyuki; Suzuki, Katsuo
JAERI-Research 96-048, 50 Pages, 1996/09
JAERI-Research-96-048.pdf:1.22MB
no abstracts in English
PNC TN9410 96-154, 103 Pages, 1996/07
Temperature response test was conducted using the sodium loop facility of structural engineering section to confirm the characteristics of the well-type thermocouples which are used in the main cooling systems of MONJU. FEM analyses were carried out to justify the results obtained from the test in the view point of analytical study. Conclusion are as follows. (1)The same dependency for the time constant of the well-type thermocouples on the flow rate the initial temperature and the range of temperature of sodium was obtained between test and analysis. (2)It is confirmed that the time constant of the well-type thermocouples dose not depend on the film coefficient in the range of flow rate of the test, but it depends on the change rate of sodium temperature. (3)It is confirmed that the dependency of the time constant on temperature is cased by thermophysical properties of the material of the well-type thermocouples. (4)It is found from the parametric analysis of the gap width between sheath and well that the gap width affects the time constant considerably. It is supposed that the maximum delay of the time constant is about 5 to 7 second for the well-type thermocouple which has the maximum tolerance.
PNC TN9410 96-136, 92 Pages, 1996/05
Thermal striping phenomena characterized by stationary random temperature fluctuations are observed in the region immediately above the core exit of liquid-metal-cooled fast breeder reactors (LMFBRs) due to the interactions of cold sodium flowing out of a control rod (C/R) assembly and hot sodium flowing out of adjacent fuel assemblies (F/As). Therefore the in-vessel components located in the core outlet region, such as upper core structure (UCS), flow guide tube, C/R upper guide tube, etc, must be protected against the stationary random thermal process which might induce high-cycle fatigue. In this study, thermally response characteristics of the flow guide tube made by SUS 316 stainless steels were investigated using a boundary element method code BEMSET under the temperature transient conditions of Sine wave, quasi-random wave, and Sine wave with quasi-random components. From the numerical investigations, it was concluded that the detailed handling on turbulence phenomena in coolant is very important in the evaluation of actual LMFBRs, because of the thermally response of the structures are influenced significantly on random fluctuating components.
; Miyoshi, Yoshinori; *; *; *
Nuclear Technology, 102, p.125 - 136, 1993/04
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Katagiri, Masaki; Kishimoto, Maki; Terada, Hiromi; ; *; ; Ito, Hirokuni; ; Kobayashi, Fumiaki
IEEE Transactions on Nuclear Science, 37(3), p.1400 - 1404, 1990/06
Times Cited Count：3 Percentile：45.1(Engineering, Electrical & Electronic)no abstracts in English
JAERI-M 8462, 63 Pages, 1979/09
no abstracts in English
JAERI-M 8461, 25 Pages, 1979/09
no abstracts in English
Oi, Takao; Takahashi, Hirokazu*
no journal, ,
Availability of analytical solution for the disposal study of the radioactive waste and the method for utilization to the disposal study of the wastes arising from Fukushima Daiichi NPS will introduced. Also, derivation of approximate analytical solution for the nuclides release from EBS with the double diffusion media and the response characteristics will be presented.
