scholarly journals Visualization of Non-Isothermal Liquids Mixing Processes Under the Influence of External Forces

2021 ◽  
Author(s):  
Alexandr Sataev ◽  
Vyacheslav Andreev
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Dynamic Mode ◽  
Loop Model ◽  
Mixing Process ◽  
Mixing Processes ◽  
Static Mode ◽  
Experimental Stand ◽  
External Forces

The paper presents a visualization of the mixing processes of non-isothermal flows in the model of a ship's nuclear power plant under static and dynamic modes. The values obtained at the experimental stand served as the database for visualization. It is a four-loop model of the flow part of a ship's nuclear power plant. To create a dynamic mode (oscillations in one plane), the model is placed on a swinging platform. This paper shows the processes occurring during periodic pitching with a period of 4 seconds and amplitude of 15 degrees. The descending annular section of the circulation tract was chosen as the object of research. Then the resulting database was visualized using the 3DFieldPro program, where a color scale was matched to the temperature data and model coordinates, and also with the help of the OpenCV library with a high-level implementation program С++, the characteristic hot/cold vortices (spots), the boundary of the mixing process, its character in static mode (without fluctuations) and dynamic mode were analyzed. The uneven mixing process was noted, especially in the dynamic mode. The resulting tools allow you to quickly and clearly visualize these processes.

Coupling of RELAP and LabVIEW to Model a Nuclear Power Plant System Realistically

2014 ◽  
Author(s):  
J. C. Pack ◽  
Z. Fu ◽  
F. Aydogan
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Virtual Instrument ◽  
Nuclear Power ◽  
System Modeling ◽  
Loop Model ◽  
Secondary System ◽  
Loss Of Coolant Accident ◽  
Accident Scenarios ◽  
Computer Simulators

Within the study and design of a nuclear power plant extensive system modeling is necessary to determine how the reactor is going to perform in any given situation, not only in the normal performance of the reactor but also transients including unanticipated transients without scram and hypothetical accidents. One of the difficulties in the performance of this modeling is that there are often separate programs used to model the primary and other loops in multiple loop systems. When the modeling requires no interaction between the loops, this method is adequate but in many of these scenarios an understanding of the interaction loops is crucial especially in the case of transients including accident scenarios. However, each loop is generally modeled individually and there is no feedback effect between loops. The purpose of this article is to demonstrate how this coupling between the primary and secondary system of a typical PWR can be performed. The primary and secondary sides of the PWR are modeled with Reactor Excursion and Leak Analysis Program (RELAP5) and Laboratory Virtual Instrument Engineering Workbench (LabVIEW) computer simulators respectively. Primary loop model includes a four loops PWR. The coupling between RELAP5 and LabVIEW has been executed with steady state and transients, in this case a loss of coolant accident (LOCA). The results of the coupling have been compared with the typical RELAP5 results without coupling.

scholarly journals Method of Seismic Capacity Analysis of Steel Structure in Nuclear Power Plant

2021 ◽  
Vol 21 (2) ◽  
pp. 111-117
Author(s):  
Dongwon Lee ◽  
Namheoyng Lim
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Structural Integrity ◽  
Steel Structure ◽  
Related Structure ◽  
Capacity Analysis ◽  
Seismic Capacity ◽  
Design Earthquake ◽  
External Forces

A steel structure in a nuclear power plant is typically constructed next to major safety-related structures. Accordingly, the structural integrity of the steel structure must be achieved until the safety-related building is damaged by external forces. Consequently, the steel structure should have seismic capacity while maintaining the structural integrity of the surrounding safety-related structure. An optimized method for the seismic capacity against the beyond design earthquake was developed to reflect this capacity concept.

Experience in Modelling the Zaporozh’ye Nuclear Power Plant Using RELAP5

2002 ◽  
Author(s):  
Vyacheslav V. Sverdlov ◽  
Alexey V. Sverdlov
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Present Model ◽  
Loop Model ◽  
Steam Generators ◽  
3 Dimensional ◽  
Plant Equipment ◽  
Core Cooling ◽  
Operating Instructions

Unit 5 of the Zaporozh’ye Nuclear Power Plant (ZNPP5), equipped with a VVER-1000/320 4-loop reactor, has been modelled in detail using the RELAP5/MOD3.2 thermal-hydraulic system code (Ref. 1). The 4-loop model affords a fidelity with ZNPP5 in terms of the system geometry such as the point of emergency core cooling (ECC) injection, for example. Both the reactor vessel and steam generators were nodalized in a quasi 3-dimensional (3-D) fashion thus allowing to capture asymmetric effects in the main reactor system components and realistic heat transfer distribution in the steam generators. Besides its use for accident analysis, the present model is intended to closely simulate operational events such as pre- and post calculations of anticipated transients and tests. At present, the model is used to support justification of the new — symptom-oriented — set of emergency operating instructions. ZNPP5 makes use of both digital and analog controls. They have been modelled in the RELAP5 model allowing to analyse in detail workings of various plant equipment. The present model was validated using three ZNPP5 transient events.

scholarly journals A simulation study of processes for mixing non-isothermal flows under dynamic effects

2020 ◽  
Author(s):  
Aleksandr Sataev ◽  
Vyacheslav Andreev ◽  
Denis Novikov ◽  
Julia Perevezentseva
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Vertical Component ◽  
Dynamic Force ◽  
Mixing Processes ◽  
Periodic Effect ◽  
Temperature Pulsations ◽  
Isothermal Flows ◽  
Isothermal Water

The processes for mixing of non-isothermal streams essentially define the parameters of the heat-carrier on an input in a core in modes with incomplete structure of the working equipment and, as a consequence, - a heat engineering condition of a core. Besides, the task of researching the temperature pulsations accompanying practically all modes of currents for non-isothermal streams is extremely relevant, as these pulsations lead to additional thermocyclic loadings on elements of the equipment and in many cases define its resource. The paper describes the research of mixing processes for non-isothermal water coolant flows in hydraulic model of ship nuclear power plant. In several experiments, attention was paid to the mixing processes when feeding non-isothermal flows through the circulation loops located opposite of each other. To simulate the effect of external dynamic force in the form of periodic effect on the spatial orientation of the model, the ship was tested on a stand "Swinging platform". These vibrations affected the mixing processes occurring within the model. The main impact they had on the transition time, temperature gradient, vertical component of the velocity projection. In the future, these parameters will be clarified and the influence of other factors on the mixing of non-isothermal flows in the ship's nuclear power plant will be studied in more detail.

Fuzzy multi-objective decision making approach for nuclear power plant installation

2020 ◽  
Vol 39 (5) ◽  
pp. 6339-6350
Author(s):  
Esra Çakır ◽  
Ziya Ulukan
Keyword(s):  
Linear Programming ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Energy Supply ◽  
Energy Demand ◽  
Nuclear Power ◽  
Power Plants ◽  
Total Duration ◽  
Objective Functions ◽  
Multi Objective

Due to the increase in energy demand, many countries suffer from energy poverty because of insufficient and expensive energy supply. Plans to use alternative power like nuclear power for electricity generation are being revived among developing countries. Decisions for installation of power plants need to be based on careful assessment of future energy supply and demand, economic and financial implications and requirements for technology transfer. Since the problem involves many vague parameters, a fuzzy model should be an appropriate approach for dealing with this problem. This study develops a Fuzzy Multi-Objective Linear Programming (FMOLP) model for solving the nuclear power plant installation problem in fuzzy environment. FMOLP approach is recommended for cases where the objective functions are imprecise and can only be stated within a certain threshold level. The proposed model attempts to minimize total duration time, total cost and maximize the total crash time of the installation project. By using FMOLP, the weighted additive technique can also be applied in order to transform the model into Fuzzy Multiple Weighted-Objective Linear Programming (FMWOLP) to control the objective values such that all decision makers target on each criterion can be met. The optimum solution with the achievement level for both of the models (FMOLP and FMWOLP) are compared with each other. FMWOLP results in better performance as the overall degree of satisfaction depends on the weight given to the objective functions. A numerical example demonstrates the feasibility of applying the proposed models to nuclear power plant installation problem.

Sign in / Sign up

Export Citation Format

Share Document