Numerical Investigation on Flow Excursion Boundary of a Full Power Natural Circulation Reactor
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概要
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An experiment was performed on the natural circulation test loop HRTL-5, which simulates the geometry and system design of the 5 MW full power natural circulation nuclear heating reactor. Different flow modes, including density wave oscillation and flow excursion et al., were observed in a wide range of inlet sub-cooling at 1.5 MPa. By means of self-developed computational codes, the bifurcation chart has been obtained. Consequently the flow excursion boundary has been determined. Through the analysis on the excursion boundary, the method to avoid the flow excursion during startup has been presented. Analytical results show: (1) with the decreasing heat flux or the increasing system pressure, the static flow excursion occurs at higher inlet temperature and its range in the instability maps becomes narrower correspondingly; (2) to decrease the outlet two-phase resistance or increase the inlet single-phase resistance is beneficial to avoid the flow excursion; (3) by means of increasing the system pressure to start up the reactor with low heat flux, the flow excursion and low steam quality density wave oscillation can be successfully avoided. This investigation is meaningful to the reactor safety and the design of the nuclear heating reactors.
- 社団法人 日本原子力学会の論文
- 2005-03-25
著者
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Jiang Sheng
Institute Of Nuclear Energy Technology Tsinghua University
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YANG Xing
Institute of Nuclear Energy Technology, Tsinghua University
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ZHANG You
Institute of Nuclear Energy Technology, Tsinghua University
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Zhang You
Institute Of Nuclear Energy Technology Tsinghua University
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Yang Xing
Institute Of Nuclear Energy Technology Tsinghua University