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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

胡大芬 杨景超 刘言午 陈涛 冉小兵

压力容器2024,Vol.41Issue(3):24-29,6.
压力容器2024,Vol.41Issue(3):24-29,6.DOI:10.3969/j.issn.1001-4837.2024.03.004

新型反应堆压力容器主螺栓螺纹副性能试验研究

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

胡大芬 1杨景超 1刘言午 1陈涛 1冉小兵1

作者信息

  • 1. 深圳中广核工程设计有限公司,广东深圳 518172
  • 折叠

摘要

Abstract

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.

关键词

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

Key words

reactor pressure vessel/main stud screw thread pair/screwing simulation test/tensile simulation test

分类

机械制造

引用本文复制引用

胡大芬,杨景超,刘言午,陈涛,冉小兵..新型反应堆压力容器主螺栓螺纹副性能试验研究[J].压力容器,2024,41(3):24-29,6.

压力容器

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1001-4837

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