Simulation of Earthquake Vibration Effects on a Reactor Fuel Element
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概要
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A UCLA reactor fuel element was subjected to forced vibration tests to determine if vibra-tion-induced changes in the moderator-coolant channel width could cause reactor power fluctuations during an earthquake. The response of the fuel element was monitored by foil-strain gages while the element was vibrated in water. At the natural frequency of the fuel element (11.1) cps, an average coolant channel width increase of 0.0009 in. was observed. We estimate that fuel vibrations with this amplitude could cause a maximum power change of 2.8 % in the UCLA reactor.<BR>Several interesting conclusions can be drawn from this work. First, based on our "worst case" analysis it appears that earthquake-induced power oscillations do not pose a reactor safety problem. Careful design (especially to increase rigidity) of fuel elements for power reactors could make the problem of vibration-induced power transients negligible. Second, using the techniques described in the report, it is possible to perform out-of-core experiments on reactor fuel elements that accurately predict the in-core dynamic response. The technique may be useful in determining the dynamic response of fuel elements under conditions where direct measurements are difficult; i.e., pressurized water reactors or liquid metal-cooled reactors.
- 一般社団法人 日本原子力学会の論文
著者
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SMITH C.
Nuclear Energy Laboratory, School of Engineering and Applied Science, University of California
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RUDMAN R.
Nuclear Energy Laboratory, School of Engineering and Applied Science, University of California