Analysis of Weld Residual Stress of J-Groove Weld in Penetrate Part

被引：0

作者：

Lin B. ^{[1
]}

Xu X. ^{[1
]}

Jin T. ^{[1
]}

Kong X. ^{[1
]}

Liu P. ^{[1
]}

Lu W. ^{[1
]}

Nie Z. ^{[1
]}

机构：

[1] State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co. Ltd., Shenzhen, 518172, Guangdong

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2020年 / 41卷 / 01期

关键词：

Hardening behavior; Heat source; J-shaped groove; Weld geometry; Welding residual stress;

D O I：

10.13832/j.jnpe.2020.01.0070

中图分类号：

学科分类号：

摘要：

In nuclear power plants, the stress corrosion cracking (SCC) is the main reason to cause the cracks in the control rod drive mechanism (CRDM) nozzle with the J-groove attachment weld to the reactor pressure vessel (RPV) head. However, SCC is mainly driven by welding residual stresses. Thus 2D axisymmetric model is used to study the weld residual stress distribution in J-shaped groove. In order to obtain a simple, efficient and conservative method, the effect of simplification of heat source, simplification of weld geometry, weld material yield strength, phase transformation, and material hardening behavior on the welding residual stress is investigated. The research result shows that the double ellipsoid heat source and uniform heat source lead to the same weld residual stress distribution; the simplification of scale weld model to block weld model has little influence on the result, but the simplification to dumped weld model could produce relatively great variation on weld residual stress distribution; low yield strength could not obtain the conservative result; in ANSYS, the phase transformation has no effect on the stress result; the result by the isotropic hardening behavior is higher about two times than that by kinematic hardening behavior; for the welding simulation in engineering, the uniform heat source, block weld model, and isotropic hardening behavior are suggested. © 2020, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：70 / 74

页数：4

共 7 条

[1] Watson C.T., Gregg A., Dennis R., Et al., Residual stress finite element analysis and measurements of a tube penetration j-groove attachment weld in a hemispherical head of a large ferritic pressure vessel: Part I Centre Nozzle, ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference, pp. 859-870, (2006)
[2] Kiyoshima S., Deng D., Ogawa K., Et al., Influences of heat source model on welding residual stress and distortion in a multi-pass J-groove joint, Computational Materials Science, 46, 4, pp. 987-995, (2009)
[3] Bae H.Y., Kim Y.J., Kim J.H., Et al., Prediction of residual stress distribution for rpv crdm penetration nozzles, ASME 2012 Pressure Vessels and Piping Conference, pp. 1165-1178, (2012)
[4] Goldak J., Chakravarti A., Bibby M., A new finite element model for welding heat sources, Metallurgical and Materials Transactions B, 15, 2, pp. 299-305, (1984)
[5] Design and construction rules for mechanical components of PWR nuclear islands. RCC-M: Section I, Subsection Z, Annex ZI., pp. 34-38, (2007)
[6] Suanno R.L.M., Teughels A., Ferrari L.D.B., Et al., Weld residual stress predictions in reactor vessel head penetrations, ASME 2009 Pressure Vessels and Piping Conference, pp. 959-971, (2009)
[7] Rudland D., Wilkowski G., Wang Y.Y., Et al., Development of circumferential through-wall crack K-solutions for control rod drive mechanism nozzles, International Journal of Pressure Vessels & Piping, 81, 12, pp. 961-969, (2004)

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