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基于大型熔融池换热特性试验装置COPRA,开展了严重事故压力容器下封头内堆芯熔融物换热特性的试验研究。试验段是1/4圆二维切片结构,内半径2.2m,与国内某自主设计三代核电堆型下封头呈1∶1比例,试验采用非共晶摩尔比例20%NaNO_3-80%KNO_3混合物作为熔融物模拟物。熔融池瑞利数可达到1016量级,与反应堆真实情况下的量级一致。试验研究了不同熔融物注入位置、熔融池高度、加热功率和注入次数等对熔融池温度场和热流密度分布的影响。结果表明,在同等瑞利数量级下,COPRA试验得到的熔融池向下封头壁面传热的Nu较国际上其他试验得到的结果低。
Based on the large-scale melting pool heat transfer characteristics test device COPRA, the experimental study on the heat transfer characteristics of the core melt in the head of a serious accident pressure vessel was carried out. The experimental section is a quarter-circular two-dimensional slice structure with an inner radius of 2.2m. The test section is in a ratio of 1: 1 to the head of a self-designed nuclear reactor of the third generation. The experiment uses a mixture of 20% NaNO 3 - 80% KNO 3 As a melt simulant. Melting pool Rayleigh number can reach 1016 orders of magnitude, with the reactor under the real situation of the same order of magnitude. The effects of different molten material injection locations, molten pool height, heating power and injection times on the temperature field and heat flux density distribution in the molten pool were studied. The results show that under the same Rayleigh order, the Nu of the COPRA test is lower than that obtained by other experiments in the world.