Analysis of Heat Transfer Characteristics in Core of Supercritical Water Cooled Reactor
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摘要: 选取了7种最为广泛应用的超临界水换热关系式,计算分析了超临界水冷堆设计工况下堆芯的传热能力。结果表明,采用不同的公式计算出的平均管出口壁温最大相差27℃。采用Koshizuka-Oka公式,热管流量与平均管相同就可满足壁温安全限值;采用Jackson公式,热管流量需比平均管高18%;采用Krasnoshchekov公式,热管流量则需比平均管高40%才能满足壁温安全限值。这说明,采用不同的换热公式会严重地影响堆芯的设计。在超临界水冷堆的设计条件下浮力对传热的影响可以忽略。Abstract: Seven most widely used heat transfer correlations were employed to calculate and analyze the heat transfer capacity in the core of Supercritical Water Cooled Reactor（SWCR） on rated condition.The results showed that maximum discrepancy of outlet clad temperature on average channel employing various correlations is 27℃.The results also showed that the clad surface temperature limitation could be satisfied even using same flowrate as average channel in hot channel when Koshizuka-Oka correlation is applied.However,18% and 40% more coolant flowrate must be distributed into hot channel than average channel if Jackson correlation and Krasnoshchekov correlation is employed respectively.It could be concluded that the choice of heat transfer correlation will seriously affect the reactor design.It was also found that the effect of buoyancy on heat transfer could be ignored on rated condition of SWCR.
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Key words:
- Supercritical water cooled reactor /
- Heat transfer characteristic /
- Core
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