Optimisation of helical geometry of inspection probe for steam generator tubes of the PFBR

2021 ◽  
Vol 63 (10) ◽  
pp. 585-591
Author(s):  
G Perumalsamy ◽  
P Visweswaran ◽  
D Jagadishan ◽  
S Joseph Winston ◽  
S Murugan

The steam generator (SG) tubes of the prototype fast breeder reactor (PFBR) located in Kalpakkam, India, need to be periodically inspected using the remote field eddy current (RFEC) technique. During the pre-service inspection of the SG tubes, it was found that the RFEC probes experienced frequent mechanical breakages. To avoid these failures, changes in the existing structural design of the RFEC probe were required. A helical groove design was proposed to obtain a smooth transition in the variation of stress across the probe during the inspection. It was difficult to calculate the flexural stiffness of the proposed helical geometry probe due to the varying cross-section along its length. In this paper, the smearing approach adopted to calculate the stiffness of the RFEC probe and the sensitivity analysis carried out to determine the optimal design of the probe are discussed. A probe was fabricated based on the helical groove design and tested to qualify its suitability for the SG inspection. The RFEC probe with helical grooves was employed for the pre-service inspection of the SG tubes of the PFBR. More than 200 tubes have been inspected using the proposed design and no mechanical failure of the probe has been observed.

2015 ◽  
Vol 83 ◽  
pp. 57-64 ◽  
Author(s):  
W. Sharatchandra Singh ◽  
B. Purnachandra Rao ◽  
S. Thirunavukkarasu ◽  
S. Mahadevan ◽  
C.K. Mukhopadhyay ◽  
...  

Author(s):  
Jae Bong Lee ◽  
Jai Hak Park ◽  
Hong-Deok Kim ◽  
Han-Sub Chung ◽  
Tae Ryong Kim

A statistical assessment model for structural integrity of steam generator tubes was proposed using Monte Carlo method. The growth of flaws in steam generator tubes was predicted using statistical approaches. The statistical parameters that represent the characteristics of flaw growth and initiation were derived from in-service inspection (ISI) non-destructive evaluation (NDE) data. Based on the statistical approaches, flaw growth models were proposed and applied to predict distribution of flaw size at the end of cycle (EOC). Because NDE measurement results differ from that of real ones in steam generator tubes, a simple method for predicting the physical number of flaws from periodic in-service inspection data was proposed. The probabilistic flaw growth rate was calculated from the in-service non-destructive inspection data. And the statistical growth of flaw was simulated using the Monte Carlo method. Probabilistic distributions of the flaw size and the probability of burst were obtained from numerously repeated simulations using the proposed assessment model.


Author(s):  
Ovidiu Mihalache ◽  
Yoshiyuki Imai ◽  
Masashi Ueda ◽  
Takuya Yamashita

The present paper describes and clarifies the main difficulties arising in the 3D numerical simulations using finite element method of the remote field eddy current effect in magnetic steam generator tubes. The 2D axisymmetric and full 3D simulations are compared with experimental results from outer discontinuities in Monju fast breeder reactor steam generator tubes. Very good agreements were obtained between measurements and 2D simulations. The influences of several parameters are evaluated by 3D simulations: convergence error of the iterative matrix solutions, pattern of the mesh discretization, the boundary limit and finite element interpolation order. The computational cost of the remote field 3D model in Monju steam generator tubes and the numerical aspects of the 3D simulations are discussed in detail in the paper.


Ultrasonics ◽  
2019 ◽  
Vol 93 ◽  
pp. 112-121 ◽  
Author(s):  
M.M. Narayanan ◽  
Anish Kumar ◽  
S. Thirunavukkarasu ◽  
C.K. Mukhopadhyay

Author(s):  
Mitch Hokazono ◽  
Clayton T. Smith

Integral light-water reactor designs propose the use of steam generators located within the reactor vessel. Steam generator tubes in these designs must withstand external pressure loadings to prevent buckling, which is affected by material strength, fabrication techniques, chemical environment and tube geometry. Experience with fired tube boilers has shown that buckling in boiler tubes is greatly alleviated by controlling ovality in bends when the tubes are fabricated. Light water reactor steam generator pressures will not cause a buckling problem in steam generators with reasonable fabrication limits on tube ovality and wall thinning. Utilizing existing Code rules, there is a significant design margin, even for the maximum differential pressure case. With reasonable bend design and fabrication limits the helical steam generator thermodynamic advantages can be realized without a buckling concern. This paper describes a theoretical methodology for determining allowable external pressure for steam generator tubes subject to tube ovality based on ASME Section III Code Case N-759-2 rules. A parametric study of the results of this methodology applied to an elliptical cross section with varying wall thicknesses, tube diameters, and ovality values is also presented.


1980 ◽  
Vol 47 (2) ◽  
pp. 257-267
Author(s):  
K. J. Longua ◽  
G. K. Whitham ◽  
C. C. Allen

Sign in / Sign up

Export Citation Format

Share Document