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PNC TN9410 97-039, 187 Pages, 1997/05
A numerical evaluation system, which is consisted of four codes, AQUA, DINUS-3, THEMIS and BEMSET has been developed for thermal striping phenomena. To validate the system for the phenomena, thermally fluid - structure interaction analysis was carried out using a existing sodium experiment of parallel impinging jet simulating the outlet region of an LMFBR core. Calculational results on the RMS values of temperature fluctuation, the histograms of temperature amplitudes and frequencies, the auto-power spectral density distributions of temperature fluctuations and the damping characteristics of temperature fluctuations showed good agreement with the measured values under the test conditions of various flow velocity. From the comparisons with the experimental data, it was concluded that the numerical evaluation system is applicable to the evaluation of thermally fluid - structure interaction phenomena related to the thermal striping.
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.
Yoshida, Masaru; Omichi, Hideki; Katakai, Ryoichi*
European Polymer Journal, 28(9), p.1141 - 1145, 1992/00
Times Cited Count：26 Percentile：72.90(Polymer Science)no abstracts in English
Hashimoto, Kazuichiro; Onizawa, Kunio; Kurihara, Ryoichi; Kawasaki, Satoru; Soda, Kunihisa;
Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. F, p.123 - 128, 1991/08
no abstracts in English
; ; ; ; ; ; ; Aizawa, Kiyoto;
PNC TN241 81-28, 292 Pages, 1981/11
Computer codes for safety analysis, including systems codes, which are used for the evaluation of LMFBR plants, have been developed along with the progress of the construction and the operation of experimental fast reactor "JOYO". On the other hand, a large number of data has been accumulated at O-arai Engineering Center and other laboratories both in Japan and abroad with the advance of safety R&D on Liquid Metal Fast Breeder Reactor (LMFBR). Various models of analysis have been proposed and many computer codes have been developed which are based on these models. This paper describes the essential part of the models and the functions of the codes, thus developed, which are used for the safety evaluation of LMFBR plant such as the prototype fast breeder reactor "MONJU".
