scholarly journals Reduction of Residual Stress on Nuclear Reactor Internals by Water Jet Peening

2005 ◽  
Vol 74 (7) ◽  
pp. 469-472
Author(s):  
Noboru SAITOU ◽  
Ren MORINAKA
2009 ◽  
Vol 2009 (0) ◽  
pp. 328-330
Author(s):  
Fujio Yoshikubo ◽  
Kouichi Kurosawa ◽  
Akihiro Kanno ◽  
Takashi Inada ◽  
Noboru Saitou ◽  
...  

Author(s):  
S. W. Glass ◽  
B. Thigpen ◽  
J. Renshaw

As many nuclear plants approach the end of their initial 40 year license period, inspection or replacement of their reactor internals bolts must be considered. This is consistent with the Materials Reliability Program (MRP 227/228) guideline for plant life extension [1,2]. Assurance of the internals structural integrity is essential for continued safe operation of these plants. If there is no suspicion or indication of bolt failure, simple inspection is normally more cost-effective than replacement. Inspection vendors have inspected thousands of internals bolts with conventional and Phased Array UT but different head configurations and bolt capture mechanisms mandate specific qualifications for each bolt type. In some cases, complex bolt and head geometries coupled with counter-bore and locking bar interferences render classical UT inspections difficult or impossible. A range of solutions to inspect reactor internals including these difficult-to-inspect-by-conventional-UT baffle bolts has been developed by several vendors [3]. This presentation references developments to make bolt inspection a relatively quick and easy task through adaptations to the SUSI submarine inspection platform, the extensive UT qualification work suitable for conventional UT plus more recent advanced nonlinear resonant techniques to distinguish between flawed or loose, vs. acceptable bolts where conventional UT cannot be applied. Initial evaluations show that these advanced techniques may have the ability to reliably detect smaller flaws than previously possible with conventional techniques as well as provide information on bolt tightness.


Author(s):  
Francis H. Ku ◽  
Pete C. Riccardella

This paper presents a fast finite element analysis (FEA) model to efficiently predict the residual stresses in a feeder elbow in a CANDU nuclear reactor coolant system throughout the various stages of the manufacturing and welding processes, including elbow forming, Grayloc hub weld, and weld overlay application. The finite element (FE) method employs optimized FEA procedure along with three-dimensional (3-D) elastic-plastic technology and large deformation capability to predict the residual stresses due to the feeder forming and various welding processes. The results demonstrate that the fast FEA method captures the residual stress trends with acceptable accuracy and, hence, provides an efficient and practical tool for performing complicated parametric 3-D weld residual stress studies.


2013 ◽  
Vol 768-769 ◽  
pp. 564-571 ◽  
Author(s):  
Kenji Suzuki ◽  
Takahisa Shobu ◽  
Ayumi Shiro

The specimen material was austenitic stainless steel, SUS316L. The residual stress was induced by water-jet peening. The residual stress was measured using the 311 diffraction with conventional X-rays. The measured residual stress showed the equi-biaxial stress state. To investigate thermal stability of the residual stress, the specimen was aged thermally at 773 K in air to 1000 h. The residual stress kept the equi-biaxial stress state against the thermal aging. Lattice plane dependency of the residual stress induced by water-jet peening was evaluated using hard synchrotron X-rays. The residual stress measured by the soft lattice plane showed the equi-biaxial stress state, but the residual stress measured by the hard lattice plane did not. In addition, the distributions of the residual stress in the depth direction were measured using a strain scanning method with hard synchrotron X-rays and neutrons.


Author(s):  
Jinya Katsuyama ◽  
Wataru Asano ◽  
Kunio Onizawa ◽  
Masahito Mochizuki ◽  
Masao Toyoda

Stress corrosion cracking (SCC) of core internals and/or recirculation pipes of austenite stainless steel (Type 316L) has been observed. When a SCC is detected at the reactor internals or pipes, it is necessary to calculate crack growth behavior of the crack for a certain operational period. The SCC initiates and grows near the welding zone because of high tensile residual stress by welding relative to the other contributing factors of material and environment. Therefore, the residual stress analysis due to welds of austenitic stainless piping is becoming important and has been already conducted by many researchers. In present work, the through-thickness residual stress distributions near multi-pass butt-welds of Type 316L pipes have been calculated by thermo-elastic-plastic analyses with the geometric and welding conditions changed and collected from literatures. Then crack growth simulations were performed using calculated and collected residual stress distributions. The effects of geometric and welding conditions on crack growth behavior were also discussed.


Author(s):  
Masahito Mochizuki ◽  
Shinsuke Itoh

Shroud head in a steam separator of ABWR is connected to more than 300 pipes, which are attached by fillet welds. Although the welding causes welding deformation, it is impossible to correct this deformation to the shroud head because the shroud head material is very thick; more than 50 mm. Thus, it is necessary to clarify the mechanism of welding deformation so that it can be quantitatively predicted and controlled. SCC prevention is also essential by residual stress control in reactor internals. The objective of this paper is to predict welding deformation and residual stress for a shroud head, and to investigate the influence of factors such as the inclination angle of the base plate, to which the pipes are connected, on welding deformation and residual stress. Million-finite-element-order large-scale computational method of residual stress and weld distortion has been developed in order to apply directy to complicated weld structures. Details of algorithm and some applications are introduced.


2013 ◽  
Vol 345 ◽  
pp. 312-315 ◽  
Author(s):  
Bing Han ◽  
Yan Hua Wang ◽  
Chang Liang Xu

Water-jet cavitation peening is a new technology for surface modification of metallic materials. Compress residual stress layer is induced by impact wave pressure in the submerged cavitating jets processing. Based on ANSYS/LS-DYNA finite element analysis software, residual stress field in the SAE1070 spring steel material surface induced by cavitate-jet water peening process is simulated, the magnitude and variation rules of the residual stress along the layer depth under different conditions is obtained. In order to verify the correctness of the numerical simulation, the size and distribution of residual stress by the X-ray diffraction method. The results show that the numerical simulation and experimental results are well consistent.


2009 ◽  
Vol 2009 (0) ◽  
pp. 335-336
Author(s):  
Hisamitsu HATOU ◽  
Fujio YOSHIKUBO ◽  
Nobuyoshi YANAGIDA ◽  
Yoshimi SATOH ◽  
Yoshihiro TOYAMA

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