Development of mechanistic boiling two-phase flow analysis methods for the design of high-power density light water reactors
| Project/Area Number |
20360419
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| Research Category |
Grant-in-Aid for Scientific Research (B)
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| Allocation Type | Single-year Grants |
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| Section | 一般 |
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| Research Field |
Nuclear engineering
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| Research Institution | Osaka University |
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Principal Investigator |
OKAWA Tomio Osaka University, 工学研究科, 准教授 (20314362)
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| Project Period (FY) |
2008 – 2010
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| Project Status |
Completed (Fiscal Year 2010)
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| Budget Amount *help |
¥19,110,000 (Direct Cost: ¥14,700,000、Indirect Cost: ¥4,410,000)
Fiscal Year 2010: ¥1,690,000 (Direct Cost: ¥1,300,000、Indirect Cost: ¥390,000)
Fiscal Year 2009: ¥3,640,000 (Direct Cost: ¥2,800,000、Indirect Cost: ¥840,000)
Fiscal Year 2008: ¥13,780,000 (Direct Cost: ¥10,600,000、Indirect Cost: ¥3,180,000)
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| Keywords | 沸騰流 / 気液二相流 / 限界熱流束 / ボイド率 / ドライアウト / 流量振動 / 非線形波動理論 / 気泡挙動 / 強制対流沸騰 / 液膜ドライアウト / サブクール沸騰 / 濡れ性 / 相変化伝熱 / 不安定 / 表面濡れ性 |
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| Research Abstract |
In high-power-density tight-lattice LWRs, margin to the onset of flow instability is reduced comparing with conventional ones. The mechanisms of the transition to the CHF condition under flow oscillation conditions were hence investigated theoretically, numerically, and experimentally. It was revealed that the nonlinear wave theory can be applied to the prediction of CHF in this situation. Void fraction in subcooled boiling region is of importance in evaluating the hydraulic stability and fuel burn-up. It was demonstrated that heat transfer enhancement by sliding bubbles and bubble coalescence play important roles in determining the axial development of the void fraction.
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Report
(4 results)
Research Products
(29 results)
