Unit for the Heat Treatment and Straightening of Tubes Used in the Steam Generators of Nuclear Power Plants

Metallurgist ◽  
2016 ◽  
Vol 60 (1-2) ◽  
pp. 61-68 ◽  
Author(s):  
S. P. Burkin ◽  
G. V. Shimov ◽  
An. V. Serebryakov ◽  
Al. V. Serebryakov
2020 ◽  
Vol 12 (12) ◽  
pp. 5149
Author(s):  
Ga Hyun Chun ◽  
Jin-ho Park ◽  
Jae Hak Cheong

Although the generation of large components from nuclear power plants is expected to gradually increase in the future, comprehensive studies on the radiological risks of the predisposal management of large components have been rarely reported in open literature. With a view to generalizing the assessment framework for the radiological risks of the processing and transport of a representative large component—a steam generator—12 scenarios were modeled in this study based on past experiences and practices. In addition, the general pathway dose factors normalized to the unit activity concentration of radionuclides for processing and transportation were derived. Using the general pathway dose factors, as derived using the approach established in this study, a specific assessment was conducted for steam generators from a pressurized water reactor (PWR) or a pressurized heavy water reactor (PHWR) in Korea. In order to demonstrate the applicability of the developed approach, radiation doses reported from actual experiences and studies are compared to the calculated values in this study. The applicability of special arrangement transportation of steam generators assumed in this study is evaluated in accordance with international guidance. The generalized approach to assessing the radiation doses can be used to support optimizing the predisposal management of large components in terms of radiological risk.


2021 ◽  
Vol 131 ◽  
pp. 103580
Author(s):  
Luca Pinciroli ◽  
Piero Baraldi ◽  
Ahmed Shokry ◽  
Enrico Zio ◽  
Redouane Seraoui ◽  
...  

Author(s):  
Murat Bakirov ◽  
Sergei Chubarov ◽  
Nikolay Trunov

The basic method of the operational inspection of metal of heat exchanging tubes (HET) of steam generators (SG) is eddy-current multifrequency method all over the world. The greatest distribution was received variant with eddy-current testing (ECT) by use of a bobbing probe on the Russian nuclear power plants (NPP). Tubes with the defects which a subject to plugging are defined by results of lead operational ECT over the certain algorithm. SG resource is settled and replacement is required at achievement of a limit on number of the plugged tubes [1].


Atomic Energy ◽  
2012 ◽  
Vol 111 (4) ◽  
pp. 276-281
Author(s):  
D. N. Babkin ◽  
N. A. Prokhorov ◽  
V. T. Sorokin ◽  
A. V. Demin ◽  
V. V. Iroshnikov

Atomic Energy ◽  
2008 ◽  
Vol 105 (3) ◽  
pp. 165-174 ◽  
Author(s):  
N. B. Trunov ◽  
B. I. Lukasevich ◽  
D. O. Veselov ◽  
Yu. G. Dragunov

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