Method for diagnostics of coolant leaks in the first loop into the boiler water of steam generators in nuclear power plants with VVÉR-440 and -1000 reactors

Atomic Energy ◽  
1994 ◽  
Vol 77 (1) ◽  
pp. 543-548
Author(s):  
E. A. Ivanov ◽  
I. V. Pyrkov ◽  
L. P. Kham'yanov
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Steam Generators ◽  
Boiler Water

scholarly journals Calculation of Potential Radiation Doses Associated with Predisposal Management of Dismantled Steam Generators from Nuclear Power Plants

2020 ◽  
Vol 12 (12) ◽  
pp. 5149
Author(s):  
Ga Hyun Chun ◽  
Jin-ho Park ◽  
Jae Hak Cheong
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Doses ◽  
Steam Generators ◽  
Pressurized Water ◽  
Water Reactor ◽  
General Pathway ◽  
Heavy Water Reactor ◽  
Past Experiences

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.

Preoperational Tests of the PIRATE Program for Identifying and Assessing the Depth of Defects in Heat Exchangers of Nuclear Power Plants’ Steam Generators

2020 ◽  
Vol 67 (8) ◽  
pp. 517-523
Author(s):  
A. G. Zhdanov ◽  
V. P. Lunin ◽  
A. A. Stolyarov ◽  
E. G. Schukis
Keyword(s):  
Heat Exchangers ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Steam Generators

A semi-supervised method for the characterization of degradation of nuclear power plants steam generators

2021 ◽  
Vol 131 ◽  
pp. 103580
Author(s):  
Luca Pinciroli ◽  
Piero Baraldi ◽  
Ahmed Shokry ◽  
Enrico Zio ◽  
Redouane Seraoui ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Steam Generators

Development of Atlas of Defects of Steam Generators Heat Exchanging Tubes of NPPs With WWER and Analysis of Testing Results

2008 ◽  
Author(s):  
Murat Bakirov ◽  
Sergei Chubarov ◽  
Nikolay Trunov
Keyword(s):  
Eddy Current ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Eddy Current Testing ◽  
Basic Method ◽  
Steam Generators ◽  
Current Testing ◽  
The World

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].

Steam generators – horizontal or vertical (which type should be used in nuclear power plants with VVER?)

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

Damage to the output manifolds of steam generators at nuclear power plants with VV�R-1000 reactors

Atomic Energy ◽  
1993 ◽  
Vol 75 (5) ◽  
pp. 896-899
Author(s):  
V. I. Baranenko ◽  
V. S. Kirov ◽  
V. P. Kravchenko ◽  
V. A. Korovkin ◽  
N. A. Fridman
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Steam Generators
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