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首页> 外文期刊>R & D 神戶製鋼技報 >原子力発電所湿分分離加熱器再熱部の性能予測手法
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原子力発電所湿分分離加熱器再熱部の性能予測手法

机译:原子力発电所湿分分离加热器再热部の性能予测手法

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摘要

Nuclear power generation uses saturated steam of 6MPa and 275℃ level due to the restrictions imposed by the materials used in the nuclear reactor, and its efficiency, approximately 33-35%, is not high compared with fossil fuel power generation. Therefore, thermal engineers working on nuclear power generation have the important responsibility toward society of achieving the highest efficiency under the given restrictions. The use of a moisture separator reheater (MSR) is one of the measures we can take to achieve higher efficiency. Because the bottom of the MSR tube bundle making contact with the cycle steam at its lowest temperature is subcooled and inadequate drainage of the condensate inside the tubes causes cyclic flooding and temperature oscillations in some cases, it is necessary to have a minimum flow rate of excess heating steam slightly beyond the demand of/what is required for the heat transfer, and the consequent subcooling must be kept below a certain level. This report describes the numerical analysis method developed for the design of heat transfer performance and evaluation of the tube bundle integrity of MSRs.
机译:由于核反应堆所用材料的限制,核能发电使用6MPa和275℃的饱和蒸汽,与化石燃料发电相比,其效率大约为33-35%。因此,从事核能发电的热工工程师在给定的限制下对社会实现最高效率负有重要责任。使用水分分离器再热器(MSR)是我们可以采取的提高效率的措施之一。由于MSR管束的底部在最低温度下与循环蒸汽接触而被过冷,并且在某些情况下,管内冷凝物的排泄不充分会引起循环溢流和温度波动,因此有必要使最小过量流量将蒸汽加热到稍微超过传热要求/所需的水平,因此必须将过冷保持在一定水平以下。本报告介绍了为设计传热性能和评估MSR的管束完整性而开发的数值分析方法。

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