Small Leak Detection by Measuring Surface Oscillation during Sodium-Water Reaction in Steam Generator
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概要
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Small leak sodium-water reaction tests were conducted to develop various kinds of leak detectors for the sodium-heated steam generator in FBR. The super-heated steam was injected into sodium in a reaction vessel having a sodium free surface, simulating the steam generator. The level gauge in the reaction vessel generated the most reliable signal among detectors, as long as the leak rates were relatively high. The level gauge signal was estimated to be the sodium surface oscillation caused by hydrogen bubbles produced in sodium-water reaction.<BR>Experimental correlation was derived, predicting the amplitude as a function of leak rate, hydrogen dissolution ratio, bubble rise velocity and other parameters concerned, assuming that the surface oscillation is in proportion to the gas hold-up. The noise amplitude under normal operation without water leak was increased with sodium flow rate and found to be well correlated with Froud number. These two correlations predict that a water leak in a "MONJU" class (300 MWe) steam generator could possibly be detected by level gauges at a leak rate above 2 g/sec.
- 一般社団法人 日本原子力学会の論文
著者
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NEI Hiromichi
O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation
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HORI Masao
O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation