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Fault Analysis and Innovation in Slag Discharge System of 440-t/h CFB Boiler
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作者 Xu Qisheng and Song Jinghui Guangdong Electric Power Test and Research Institute Wang Ningling 《Electricity》 2009年第1期34-37,共4页
CFB boilers have been widely used in China in recent years with their perfect performances in coal adaptability, load variation capability and lower pollutant emission. The No.3 135-MW CFB unit in Lianzhou Power Plant... CFB boilers have been widely used in China in recent years with their perfect performances in coal adaptability, load variation capability and lower pollutant emission. The No.3 135-MW CFB unit in Lianzhou Power Plant is the f irst 440-t/h series CFB unit in Guangdong Province. It f inished 72-hour trial operation in Feb. 2004 and was transferred to trial operation. During the trial operation and the next commercial operation, there were some problems happened in the boiler slag discharging system, seriously affecting the safe and reliable operation and the loading capability. After innovation, these problems have been completely solved. Hopefully the solutions may be used for reference to the units with similar problems. 展开更多
关键词 CFB Fault analysis and Innovation in Slag discharge System of 440-t/h CFB Boiler INNOVATION
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Multiscale analysis of spring discharge and the time-variant characteristic of Karst groundwater system
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《Global Geology》 1998年第1期73-74,共2页
关键词 TIME Multiscale analysis of spring discharge and the time-variant characteristic of Karst groundwater system
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Development of an Evaluation Methodology for Fuel Discharge in Core Disruptive Accidents of Sodium-Cooled Fast Reactors
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作者 Kenji Kamiyama Yoshiharu Tobita Tohru Suzuki Ken-ichi Matsuba 《Journal of Energy and Power Engineering》 2014年第5期785-793,共9页
The purpose of the present study is to develop a methodology to evaluate fuel discharge through the CRGT (control-rod guide tube) during CDAs (core-disruptive accidents) of SFRs (sodium-cooled fast reactors), si... The purpose of the present study is to develop a methodology to evaluate fuel discharge through the CRGT (control-rod guide tube) during CDAs (core-disruptive accidents) of SFRs (sodium-cooled fast reactors), since fuel discharge will decrease the core reactivity and CRGTs have a potential to provide an effective discharge path. Fuel discharge contains multi-component fluid dynamics with phase changes, and, in the present study, the SFR safety analysis code SIMMER (Sn, implicit, multifield, multicomponent, Eulerian recriticality) was utilized as a technical basis. First, dominant phenomena affecting fuel discharge through the CRGT are identified based on parametric calculations by the SIMMER code. Next, validations on the code models closely relating to these phenomena were carried out based on experimental data. It was shown that the SIMMER code with some model modifications could reproduce the experimental results appropriately. Through the present study, the evaluation methodology for the molten-fuel discharge through the CRGT was successfully developed. 展开更多
关键词 Sodium-cooled fast reactor core disruptive accident molten-fuel discharge FBR (fast breeder reactor) safety analysis code SIMMER.
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