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新型反应堆压力容器主螺栓螺纹副性能试验研究OA北大核心CSTPCD

Performance testing research of stud screw thread pairs of the new type reactor pressure vessel

中文摘要英文摘要

以国内某新型号压水反应堆压力容器主螺栓螺纹副为研究对象,对其进行了各安装工况下的旋拧模拟试验和拉伸标定试验.结果表明:新型主螺栓螺纹副的各安装参数推荐值可为主螺栓安装偏心度应不大于0.5 mm,主螺栓旋转速度应不大于30 rad/min,主螺栓剩余平衡配重应不大于40 kg,主螺栓允许的最大旋转力矩可不超过90 N·m;新型主螺栓剩余拉伸量计算值与拉伸标定值几乎一致,新型主螺栓绝对拉伸载荷与剩余拉伸载荷比值约为1.22,在工程经验范围值内,证明了新型主螺栓螺纹副结构设计的合理性,且新堆型主螺栓在所有工况下拉伸过程中的最大允许绝对拉伸量为4.13 mm.

Using a new type reactor pressure vessel stud screw thread pair of pressurized water reactor as the research object,the screwing simulation test and tensile simulation test of the new type reactor pressure vessel stud screw thread pair were carried out.The test results show that the recommended values of installation parameters of new stud thread pair were as follows:The stud installation eccentricity should not be more than 0.5 mm.The stud screwing speed should not be more than 30 rad/min,the stud residual balance weight should not be more than 40 kg,and the maximum allowable rotation torque of the stud can be 90 N·m.The calculated value of the new stud residual tension length was almost consistent with measured value.The ratio of absolute tensile load and residual tensile load of new stud was about 1.22,which was in the range of engineering experience,proving the rationality of structure design of the new type reactor pressure vessel stud screw thread pair.And the maximum absolute tension length of the new stud under all conditions is 4.13 mm.

胡大芬;杨景超;刘言午;陈涛;冉小兵

深圳中广核工程设计有限公司,广东深圳 518172

机械工程

反应堆压力容器主螺栓螺纹副旋拧模拟试验拉伸标定试验

reactor pressure vesselmain stud screw thread pairscrewing simulation testtensile simulation test

《压力容器》 2024 (003)

24-29 / 6

10.3969/j.issn.1001-4837.2024.03.004

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