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Yamaguchi, Akira*; Tatsumi, Eisaku*; Takata, Takashi*; Ito, Kei; Ohshima, Hiroyuki; Kamide, Hideki; Sakakibara, Jun*
Nuclear Engineering and Design, 241(5), p.1627 - 1635, 2011/05
Times Cited Count:6 Percentile:44.28(Nuclear Science & Technology)In a sodium-cooled fast reactor, inert gases exist in the primary coolant system either in a state of dissolved gas or free gas bubbles. In the present study, a gas entrainment allowance level at the free surface is discussed and rationalized. The influence of the gas entrainment is evaluated using the void fraction at the core inlet. For the purpose, a plant dynamics code VIBUL has been developed to evaluate the concentration distribution of the dissolved gas and the free gas bubble. It is noted that the background level is already very low in comparison with the induced void reactivity by the void passing the reactor core.
Yamaguchi, Akira*; Takata, Takashi*; Tatsumi, Eisaku*; Ito, Kei; Ohshima, Hiroyuki; Kamide, Hideki; Sakakibara, Jun*
Proceedings of 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7) (CD-ROM), 16 Pages, 2008/10
In a sodium-cooled fast reactor, inert gases exist in the primary coolant system either in a state of dissolved gas or free gas bubbles. The gas in the primary system may cause disturbance in reactivity, nucleation site for boiling, etc. Therefore, the allowance level is necessary regarding the gas entrainment and the gas bubble concentration. In the present study, a gas entrainment allowance level is discussed and rationalized. For the purpose, a plant dynamics code VIBUL has been developed to evaluate the concentration distribution of the dissolved gas and the free gas bubble. Assuming that the total void fraction should be kept below 105% of the background level, a preliminary design allowance level of gas entrainment is proposed as the map in terms of the entrainment ratio and the entrained bubble radius. Furthermore, the possibility of bubble removal is investigated to satisfy the allowance level.
Tatsumi, Eisaku*; Takata, Takashi*; Yamaguchi, Akira*; Ohshima, Hiroyuki; Ito, Kei; Kamide, Hideki
no journal, ,
In order to estimate inert gas behavior in a circulating system of a sodium-cooled fast reactor, the plant dynamics code called the VIBUL code has been employed. In this study, the VIBUL was used to evaluate the effect of gas entrainment phenomena at free surface in upper plenum on the void fraction at core inlet.