10MW高温气冷堆蒸汽发生器传热管束应力分析

Stress Analysis of HTR-10Steam Generator Heat Exchanging Tubes

10MW高温气冷堆蒸汽发生器SG传热管是带放射性的一回路与无放射性的给水蒸汽二回路的屏障。管束的破裂将会引起二回路的水蒸汽进入一回路,从而导致堆芯压力的升高和放射性产物的外泄,因此确保传热管的完整性是十分必要的。传热管的结构采用小弯曲半径的螺旋管结构,对于这种无法进行体积性在役检查的螺旋管,利用破前漏思想确保传热管的完整性是一个重要的选择。本文利用管道有限元程序PIPESTRESS对高温气冷堆蒸汽发生器传热管的应力进行了计算,得到了传热管的最大应力和应力与材料的不利组合位置。

Steam Generator(SG)heat exchanging tubes of 10MW High Temperature Gas Cooled Re-actor(HTR-10)are protective screens between the p rimary loop of helium with radioactivity and the sec-ondary loop of feeding water and stea m without radioactivity.Water and s team will enter into the primary loop when rupture of the heat exchanging tubes occurs,which lead to incre ase of the primary loop pressure and discharge of radioactive materials.Therefore it is important to guarantee the integrity of the tubes.The tube structure is spiral tube with sm all bending radius,which make it imp ossible to test with volumetric in-service detection.For such kind of spiral tube,using LBB concept to g uarantee the integrity of the tubes i s an important option.This paper conducts stress analysis and calculatio n of HTR-10SG heat exchanging tubes using the FEM code of piping str ess analysis,PIPESTRESS.The maxim um stress and the dangerous positions are obtained.