scholarly journals Operation and Performance Analysis of Steam Generators in Nuclear Power Plants

10.5772/66962 ◽  
2017 ◽  
Author(s):  
Siniša Šadek ◽  
Davor Grgić
Keyword(s):  
Performance Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Steam Generators ◽  
And Performance

scholarly journals APPLICATION OF MONITORING, DIAGNOSIS, AND PROGNOSIS IN THERMAL PERFORMANCE ANALYSIS FOR NUCLEAR POWER PLANTS

2014 ◽  
Vol 46 (6) ◽  
pp. 737-752 ◽  
Author(s):  
HYEONMIN KIM ◽  
MAN GYUN NA ◽  
GYUNYOUNG HEO
Keyword(s):  
Performance Analysis ◽  
Thermal Performance ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Diagnosis And Prognosis

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

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

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].

Work Structure in Nuclear Power Plants

1983 ◽  
Vol 27 (7) ◽  
pp. 571-575 ◽  
Author(s):  
Marjorie B. Bauman ◽  
Richard F. Pain ◽  
Harold P. Van Cott ◽  
Margery K. Davidson
Keyword(s):  
Critical Incident ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Primary Source ◽  
Structure Factors ◽  
Research Themes ◽  
Plant Personnel ◽  
And Performance ◽  
Work Structure

This paper describes the assessment of the work structure of ten nuclear power plants. Work structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Questionnaires given to a cross-section of personnel at the plants were the primary source of data collection. Structured “critical incident” interviews were conducted to verify the questionnaire results. The study revealed that a variety of work structure factor problem areas do exist in nuclear power plants. The paper highlights a prioritized set of candidate research themes to be considered in EPRI's Work Structure and Performance Research Program.

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
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