Critical Power in 7-Rod Tight Lattice Bundle(<Special Issue>International Conferences on Power and Energy System)
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概要
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The Reduced-Moderation Water Reactor (RMWR) has recently becomes of great concern. The RMWR is expected to promote the effective utilization of uranium recourse. The RMWR is based on water-cooled reactor technology, with achieved under lower core water volume and water flow rate. In comparison with the current light water reactors whose water-to-fuel volume ratio is about 2-3, in the RMWR, this value is reduced to less than 0.5. Thereby, there is a need to research its cooling characteristics. Experimental research on critical power in tight lattice bundle that simulates the RMWR has been carried out in Japan Atomic Energy Research Institute (JAERI). The bundle consists one center rod and six peripheral rods. The 7 rods are arranged on a 14.3mm equilateral triangular pitch. Each rod is 13mm in outside diameter. An axial 12-step power distribution is employed to simulate the complicate heating condition in RMWR. Experiments are carried out under G=100-1400kg/m^2s, P_<ex>=2-8.5MPa. Effects of mass velocity, inlet temperature, pressure, radial peaking factor and axial peaking factor on critical power and critical quality are discussed. Compared with axial uniform heating condition, the axial non-uniform heating condition causes an obvious decrease in critical quality. Arai correlation, which is the only correlation that has been optimized for tight lattice condition, is verified with the present experimental data. The correlation is found to be able to give reasonable prediction only around RMWR nominal operating condition.
- 一般社団法人日本機械学会の論文
- 2004-05-15
著者
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Liu W
Japan Atomic Energy Agency
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Liu Wei
サウサンプトン大
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Liu Wei
Japan Atomic Energy Agency
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Liu W
九大 大学院工学府
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Akimoto Hajime
Japan Atomic Energy Agency
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Akimoto H
Japan Atomic Energy Res. Inst. Ibaraki
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Akimoto Hajime
Frontier Research System For Global Change
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KURETA Masatoshi
Japan Atomic Energy Agency
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