scholarly journals Static strength calculation of DN 350 branch pipe cutting-in in the main circulation pipeline of reactor plant WWER-1000

Author(s):  
A E Ovsenev ◽  
N Pimenov ◽  
A O Semenov ◽  
I S Bibik ◽  
M M Balachkov
2020 ◽  
Vol 6 (1) ◽  
pp. 29-35
Author(s):  
Ivan V. Maksimov ◽  
Vladimir V. Perevezentsev

As operational experience shows, it can hardly be excluded that some detached or loosened parts and even foreign objects (hereinafter referred to as the ‘loose parts’) may appear in the main circulation loop of VVER reactor plants. Naturally, the sooner such incidents are detected and evaluated, the more time will be available to eliminate or at least minimize damage to the reactor plant main equipment. The paper describes a method for localizing the impact of loose parts located in the coolant circulation circuit of a VVER reactor plant. To diagnose malfunctions of the reactor plant main equipment, it is necessary to accurately determine the place where the acoustic anomaly occurred. Therefore, if some loose parts make themselves felt, it is important to track the path of their movement along the main circulation circuit as well as their location using physical barriers. The method is based on the representation of the surface, along which an acoustic wave travels, as a 3D model of the reactor plant (RP) main circulation circuit. The model has the form of a graph in which the vertices characterize the control points on the RP surface and the edges are the distances between them. The method uses information about the acoustic wave velocity and the time difference of arrivals (TDOAs) of the signal received by various sensors. It is shown that, when the effect is received by more than three sensors, along with an estimate of the impact coordinate, it becomes possible to estimate the average acoustic wave velocity. To determine time of arrival, the signal dispersion change point detection method is used. Provided that the average size between the control points on the RP surface was 300 mm, the average localization error was about 600 mm. The developed algorithm can be easily adapted to any VVER reactor plant. The obtained deviation values are acceptable for practical use.


2019 ◽  
Vol 5 (3) ◽  
pp. 249-256
Author(s):  
Vladimir P. Povarov ◽  
Anatoly I. Fedorov ◽  
Sergey L. Vitkovsky

The re-modernization of Unit 4 at the Novovoronezh NPP (Novovoronezh-4) made it possible to take a new approach to the problem of extending the VVER-440 reactor plant life and operation. The authors analyze the existing problems of the VVER-440/179 power unit, showing possible solutions to the identified shortcomings and the final state of the updated power unit. Modernization works significantly expanded the range of design-basis accidents from the primary coolant leak from an opening (DN = 100 mm) to the maximum possible, associated with a rupture of the main circulation pipelines (MCP) (DN = 500 mm). A unique experience was gained in using the safety systems of Unit 3, which was finally shutdown for decommissioning, to increase reliability and provide additional redundancy for the safety systems of Unit 4. The results of the performed works showed the correctness of the adopted concept of re-extending the service life of Unit 4 and ensured its compliance with the modern safety requirements in nuclear power engineering, including as it relates to the safety impact of the first-level probabilistic safety analysis model (PSA-1) for internal initiating events.


2020 ◽  
Vol 6 (3) ◽  
pp. 143-147
Author(s):  
Aleksandr V. Beznosov ◽  
Pavel A. Bokov ◽  
Aleksandr V. Lvov ◽  
Tatyana A. Bokova ◽  
Nikita S. Volkov ◽  
...  

The paper presents the results of the studies to justify the design solutions for the main circulation pumps of the heavy liquid-metal cooled reactor plant circuits. A substantial difference has been shown in the performance of pumps for the heavy liquid-metal coolant transfer. The studies have confirmed the qualitative difference in the cavitation performance of coolants, the state of the gases and vapors they contain, the influence of supply and discharge devices, and the effects of the impeller blade section performance and geometry and the hub-tip ratio on the pump performance. The studies were performed based on NNSTU’s lead-cooled test facilities with the coolant temperature in a range of 440 to 550 °C and the coolant flow rate of up to 2000 t/h. The outer diameter of the impellers and the straightening devices was about 200 mm, and the thickness of the flat 08Kh18N10T-steel blades was 4.0 mm and that of the airfoil blades was up to 6.0 mm. The pump shaft speed changed in a stepped manner from 600 rpm to 1100 rpm after each 100 rpm. The studies were conducted to justify the engineering and design solutions for pumps as applied to conditions of small and medium plants with fast neutron lead cooled reactors currently under investigation at NNSTU (BRS-GPG). The experimental results can be recommended for use to design other HLMC transfer pumps.


2018 ◽  
Vol 251 ◽  
pp. 04019
Author(s):  
Oleg Primin ◽  
Sergey Zotkin ◽  
Grigory Gromov

In recent years, methods of trenchless pipe reconstruction have become widely used in Russia. Once the polymer pipe pulled into the existing pipeline, the necessity of filling the intertube space with a mortar is solved. Due to the lack of clear recommendations on the implementation of the filling, builders often perform these works by trial and error. This requires special research. The article deals with an analysis of standards in this area, There is an example of a static strength calculation.


2011 ◽  
Vol 341-342 ◽  
pp. 296-300
Author(s):  
Bing Wei Ji ◽  
Jing Lu Li ◽  
Xiao Ping Chen

The method of piston pin's strength calculation base on FEA is proposed to solve the pin's failure. The pin's circular deformation is measured by node displacements, and the conventional static strength analysis is replaced by multi-case fatigue calculation. Compared with the conventional strength verification method, the FEA result is more accurate with the reality.


2021 ◽  
Vol 285 ◽  
pp. 07040
Author(s):  
Mariya Androsenko ◽  
Nail Tyuteryakov ◽  
Ekaterina Kulikova ◽  
Lyubov Deryabina ◽  
Ivan Krayniy

The paper shows an algorithm for determining the load on the electric motor of run-out conveyor starting from determination of the first moment of no load operation during slab conveying, slipping torque of the rollers along the surface of the conveyed billet and ending with the choice of the electric motor. It also covers an algorithm for strength calculations of the run-out conveyor roller, which includes the calculation of the moments and forces acting on the conveyor roller and its supports, the calculation of static strength and torsion strength, calculation of roller deflection of the conveyor rollers as well as the selection and verification calculation of conveyor roller bearings.


2020 ◽  
Vol 2020 (2) ◽  
pp. 64-72
Author(s):  
Alexander Viktorovich Beznosov ◽  
Pavel Andreevich Bokov ◽  
Aleksandr Vyacheslavovich Lvov ◽  
Tatiana Alexandrovna Bokova ◽  
Nikita Sergeevich Volkov ◽  
...  

2019 ◽  
Author(s):  
Song Deng ◽  
Yali Liu ◽  
Xia Wei ◽  
Lei Tao ◽  
Yanfeng He

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