scholarly journals Denting of Inconel steam generator tubes in pressurized water reactors. Final report

1977 ◽  
Author(s):  
D. Van Rooyen ◽  
J.R. Weeks
Keyword(s):  
Steam Generator ◽  
Pressurized Water Reactors ◽  
Final Report ◽  
Pressurized Water ◽  
Water Reactors ◽  
Steam Generator Tubes

An Automated System for Detection of Through-Wall Cracks in Racks in Steam Generator Tubes

2005 ◽  
Vol 297-300 ◽  
pp. 2071-2076 ◽  
Author(s):  
Sung Jin Song ◽  
Chang Hwan Kim ◽  
Deok Hyun Lee ◽  
Myung Sik Choi ◽  
Do Haeng Hur ◽  
...  
Keyword(s):  
Steam Generator ◽  
Automated System ◽  
Pressurized Water ◽  
Promising Tool ◽  
Primary Water ◽  
Water Reactors ◽  
The Difference ◽  
Human Operators ◽  
Shape Curve ◽  
Steam Generator Tubes

Through-wall axial cracks occurred by primary water stress corrosion are one of the serious defects in steam generator (SG) tubes (made of alloy 600) in pressurized water reactors. Therefore, it is necessary to detect and size them by eddy current testing (ECT) conducted during in-service inspection of SG tubes. To address this issue, it has been recently proposed an effective method, namely „M-shape profile“ approach, which relies on the difference in the amplitude between the pancake and plus point coils in a MRPC probe. Even though the M-shape curve approach is straightforward in principle, it requires time-consuming data processing if performed by human operators. In order to get rid of this tedious task, an automated system is developed in the present work. This paper addresses the principle of the M-shape approach together with the automated system and its performances for the detection of natural axial cracks in SG tubes. The results observed in the present work demonstrate the high potential of the developed system as a very promising tool for detecting through-wall cracks in many practical field applications.

Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)

Kerntechnik ◽  
2020 ◽  
Vol 85 (1) ◽  
pp. 54-67
Author(s):  
A. Hamedani ◽  
O. Noori-Kalkhoran ◽  
R. Ahangari ◽  
M. Gei
Keyword(s):  
Steam Generator ◽  
Nuclear Power ◽  
Axial Direction ◽  
Pressurized Water Reactors ◽  
Steam Generators ◽  
Pressurized Water ◽  
Heated Channel ◽  
Water Reactors ◽  
Secondary Side

Abstract Steam generators are one of the most important components of pressurized-water reactors. This component plays the role of heat transfer and pressure boundary between primary and secondary side fluids. The Once Through Steam Generator (OTSG) is an essential component of the integrated nuclear power system. In this paper, steady-state analysis of primary and secondary fluids in the Integral Economizer Once Through Steam Generator (IEOTSG) have been presented by Single Heated Channel (SHC) and subchannel modelling. Models have been programmed by MATLAB and FORTRAN. First, SHC model has been used for this purpose (changes are considered only in the axial direction in this model). Second, the subchannel approach that considers changes in the axial and also radial directions has been applied. Results have been compared with Babcock and Wilcox (B&W) 19- tube once through steam generator experimental data. Thermal- hydraulic profiles have been presented for steam generator using both of models. Accuracy and simplicity of SHC model and importance of localization of thermal-hydraulic profiles in subchannel approach have been proved.

scholarly journals Sources of radioiodine at pressurized water reactors. Final report

1978 ◽  
Author(s):  
C. A. Pelletier ◽  
J. E. Cline ◽  
E. D. Barefoot ◽  
R. T. Hemphill ◽  
P. G. Voilleque ◽  
...  
Keyword(s):  
Pressurized Water Reactors ◽  
Final Report ◽  
Pressurized Water ◽  
Water Reactors
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