Dynamic Response of Hot/Cold Liquid Interfaces to Pump Speed Perturbations in a Thermal-Hydraulic Loop Simulating a PIUS-type Reactor.
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- SIBAMOTO Yasuteru
- Department of Nuclear Safety Research, Japan Atomic Energy Research Institute
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- YONOMOTO Taisuke
- Department of Nuclear Safety Research, Japan Atomic Energy Research Institute
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- KUKITA Yutaka
- Department of Nuclear Safety Research, Japan Atomic Energy Research Institute
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- TSUJI Yoshiyuki
- Department of Energy Engineering and Science,Nagoya University
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- TAMAKI Masayoshi
- Department of Energy Engineering and Science,Nagoya University
書誌事項
- タイトル別名
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- Dynamic Response of Hot Cold Liquid Int
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The operation of a PIUS-type reactor requires controlling the reactor pump speed to keep stationary the hot/cold liquid interfaces between the reactor coolant and cold borated water. The dynamic response of the interface location to pump speed perturbations is analyzed for an experimental loop simulating a PIUS-type reactor. The transfer function between the pump speed and the interface location is obtained by perturbing and Laplace-transforming the one-dimensional fluid momentum equations. The analytical results agree well with experimental data taken from the same facility. It is shown that the magnitude of the phase lag in the response of the interface location, which needs to be considered in designing a pump speed controller, primarily depends on the fluid inertia in the loop, the density lock flow area, and the density difference between the simulated reactor coolant and borated water.
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 33 (9), 703-711, 1996
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390282679070539392
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- NII論文ID
- 10002075446
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK28XmsVeis7c%3D
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- ISSN
- 18811248
- 00223131
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- NDL書誌ID
- 4060427
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- NDL
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可