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Title: Study on Jet Breakup Behavior at Core Disruptive Accident for Fast Breeder Reactor

Conference ·
OSTI ID:20997044
; ;  [1];  [2];  [3];  [4]
  1. University of Tsukuba, Tsukuba, 305-8577 Ibaraki (Japan)
  2. Mitsubishi Heavy Industries, Ltd. (Japan)
  3. Advanced Reactor Technology Company, Ltd., 15-1, Tomihisa-cho, Shinjuku-ku, Tokyo 162 (Japan)
  4. University of Hyogo, Higashikawasaki-cho, Chuo-ku, Kobe-shi, Hyogo (Japan)

It is important to estimate the cooling possibility of the molten jet in coolant during a core disruptive accident (CDA) of a fast breeder reactor (FBR). In the present study, the molten jet of U-alloy 78 simulating the core material is injected into the water simulating the coolant. The visual data of the molten jet breakup behavior is observed by using the high-speed video camera. The front velocity of the molten jet is estimated by using the image processing technique from the visual data. It shows that the front velocity of the molten jet can be divided into three time regions. In the first region, the front velocity of the molten jet increases. In the second region, the front velocity of the molten jet suddenly decreases. In the third region, the front velocity of the molten jet keeps at low and steady. In first region, the column diameter of the molten jet decreases with the passage of time. At the location between first region and second region, the column of the molten jet breaks up and disappears. In the present study, the jet breakup length is defined as the distance from the water surface to the location where the jet column disappears. The results show that the jet breakup length depends on the injection nozzle diameter, but does not depend on the jet penetration velocity. This tendency agrees with the prediction by Epstein's equation. After the experiment, the solidified fragments are collected and the mass median diameter is measured. The mass median diameter is compared with the existing theories. Furthermore, a model to estimate the cooling possibility during a CDA of a FBR is constructed, reflecting the above-mentioned results. (authors)

Research Organization:
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
OSTI ID:
20997044
Resource Relation:
Conference: 14. International conference on nuclear engineering (ICONE 14), Miami - Florida (United States), 17-20 Jul 2006; Other Information: Country of input: France
Country of Publication:
United States
Language:
English