The Research of Marine Nuclear Power Two Loop Simulation Software Based on the Thermal System Analysis

2014 ◽  
Vol 983 ◽  
pp. 288-291
Author(s):  
Guo Lei Zhang ◽  
Xiang Dong Jin ◽  
Zhan Zhao ◽  
Zhi Jun Shi
Keyword(s):  
Nuclear Power ◽  
System Analysis ◽  
Simulation Analysis ◽  
Simulation Software ◽  
Operating Conditions ◽  
Two Phase ◽  
Design Data ◽  
Software Optimization ◽  
Power Simulation ◽  
Basic Functions

To study of Nuclear power simulation software's basic functions and mathematical model based on thermal analysis. Describes the two-phase flow model of GSE software superiority, as well as the software optimization program .Use of software tools for normal operating conditions of the simulation calculation and analysis of the results. Comparison with design data shows that,the software use in marine nuclear power two loop system simulation analysis field, the accuracy of it is higher.

scholarly journals Simulation Analysis of Erosion–Corrosion Behaviors of Elbow under Gas-Solid Two-Phase Flow Conditions

Lubricants ◽  
2020 ◽  
Vol 8 (9) ◽  
pp. 92
Author(s):  
Qunfeng Zeng ◽  
Wenchuang Qi
Keyword(s):  
Chemical Reaction ◽  
Simulation Analysis ◽  
Electrochemical Corrosion ◽  
Simulation Software ◽  
Solid Particles ◽  
Two Phase ◽  
Particle Count ◽  
Coal Gas ◽  
Erosion Corrosion ◽  
Corrosion Behaviors

In the production and gathering process of coal gas, the complex composition of the coal gas, harsh environments, the complex medium, and high content of solid particles in slurry cause the equipment malfunctions and even failure because of erosion and corrosion. In the present study, COMSOL multi-physics finite element simulation software is used to simulate the erosion–corrosion behaviors of elbow in key chemical equipments. The electrochemical corrosion, solid particle erosion, chemical reaction, and turbulent flow are coupled together. The particle count method is proposed to clarify the erosion phenomenon. The simulation results show that particles with high turbulent intensity hit the wall of elbow directly, which forms a slanted elliptical erosion zone on the extrados surface at 40°–50°. The chemical reaction in turbulence has a difference in the concentration distribution of substances, and this phenomenon leads to different magnitudes of the corrosion current densities in the tube. Moreover, 1/6 released particles hit the extrados surface of the elbow. These findings are beneficial to understand the erosion–corrosion phenomena and design the elbow in key chemical equipment.

Reconfigurable System Analysis for Agile Manufacturing

1996 ◽  
Author(s):  
Ashish Dhumal ◽  
Rajiv Dhawan ◽  
Anupama Kona ◽  
A. H. Soni
Keyword(s):  
System Analysis ◽  
Deterministic Model ◽  
Discrete Event ◽  
Agile Manufacturing ◽  
Simulation Software ◽  
Operating Conditions ◽  
Shop Floor ◽  
Control Logic ◽  
Design And Synthesis ◽  
Agile Enterprise

Abstract Agile manufacturing concept requires an enterprise view and agility embodies concepts like rapid prototyping, reconfigurable equipment, design for upgradability, leveled production and continuous improvement to introduce new products to the market at an affordable price. An agile enterprise needs to consider shop floor issues as well. There is an increase in use of reconfigurable tooling in industries, and much of it is in need of integration. A need exists for improvement in building of production tooling which can be reconfigured when need arises with the smallest possible changeover time. This paper analyzes different production scenarios of a forging cell designed using Petrinet theory. Petrinet theory is effective in design and synthesis of discrete event systems, especially agile systems and incorporates the control logic of the system. The objective of the study was to quantify agility of the system by determining system characteristics at different operating conditions and its ability to accommodate different products. The deterministic model is analyzed using a simulation software package. Conclusions obtained from this study are summarized for evaluation of reconfigurable systems focused on assembly aspects.

Research Based on the Simulink Excavator Hydraulic System Dynamic Simulation

2013 ◽  
Vol 694-697 ◽  
pp. 1532-1536
Author(s):  
Qiao Lian Du ◽  
Xu Hui Chen ◽  
Wei Zheng Chen
Keyword(s):  
Hydraulic System ◽  
Simulation Analysis ◽  
Circuit Simulation ◽  
Simulation Software ◽  
Operating Conditions ◽  
Hydraulic Circuit ◽  
Simulink Simulation ◽  
Improvement Measure ◽  
Working Device ◽  
System Dynamic Simulation

This paper first to the excavator bucket rod of hydraulic circuit based on the establishment of basic hydraulic components of the mathematical model, using the Simulink simulation software to build the overall hydraulic circuit simulation model; according to the actual situation of module parameters to the appropriate value, the complex and changeable load is simplified into four different operating conditions, by inputting different signals to simulate different operating condition simulation, finally through the study of the parameters on the dynamic characteristics of hydraulic system of excavator working device effects, the results of the simulation analysis, put forward the corresponding improvement measure.

scholarly journals Uncertainty quantification of RELAP5/MOD3.3 for interfacial shear stress during small break LOCA

2021 ◽  
Vol 7 (3) ◽  
pp. 1-7
Author(s):  
Hanh Tung DUONG ◽  
Hoang Anh NGUYEN ◽  
Richard TREWIN ◽  
Hiroshige KIKURA
Keyword(s):  
Shear Stress ◽  
Nuclear Power ◽  
System Analysis ◽  
Fluid Model ◽  
Interfacial Shear Stress ◽  
Reactor Core ◽  
Computer Code ◽  
Interfacial Shear ◽  
Two Phase ◽  
Two Fluid

The Best-Estimate Plus Uncertainty (BEPU) is applied as Deterministic Approach forsafety analysis of Nuclear Power Plant using the system analysis code. The system analysis code such as Relap5/Mod3.3 is required to be able to simulate the thermal-hydraulic behavior of nuclear reactor in some accident scenarios. Relap5/Mod3.3 is developed based on two-fluid models and 6 conservation equations for each phase which challenge for mathematical modeling such as onedemensional equation, time-dependent equation, multidimensional effects or complicated geometry. Thus, it is necessary to verify the applicability of a system analysis code that is able to predict accurately the two-phase flow such as interfacial shear stress between two phases: liquid and gases. It is also important to know the prediction uncertainty by using computer code due to the constitutive relation in the two-fluid model equation. In PWR’s Small-Break LOCA (SB-LOCA) accident, the loop-seal clearing is important phenomena where we would like to know how much water (reflux condensation) will be come into the reactor core from Steam Generator. In this work, the UPTFTRAM simulated the counter-current flow in Loop-seal Clearing between vapor and liquid in Loopseal during SB-LOCA is used to verify the applicability of Relap5/Mod3.3 and the experimental data are used to compare with simulation results. Moreover, the uncertainty evaluation or estimation is also investigated by applying the statistical method or BEPU in which the SUSA program developed by GRS is used.

scholarly journals Simulation System for PeLUIt 150 MW Nuclear Reactor by using vPower

2021 ◽  
Vol 2048 (1) ◽  
pp. 012034
Author(s):  
M Yunus ◽  
A A Budiman ◽  
S Zhe ◽  
Kiswanta ◽  
W Chunlin ◽  
...  
Keyword(s):  
Steady State ◽  
Steam Generator ◽  
Nuclear Power ◽  
Thermal Power ◽  
Rankine Cycle ◽  
Operating Conditions ◽  
Transient Condition ◽  
Design Data ◽  
Water Steam ◽  
Main Steam

Abstract In developing the PeLUIt 150 MW nuclear power plant based on the High Temperature Gas-cooled Reactor (HTGR) technology, with the helium-coolant and output thermal power of 150 MW, the PeLUIt simulator is also developed for training the operators and educating other technical personnel. Referred to the balance of plant (BOP) design of the PeLUIt, the simulator utilized the vPower simulation platform to simulate the secondary loop for power generation with a water-steam Rankine cycle. The paper focuses on developing the secondary loop’s main components: steam generator, steam turbine, condenser, deaerator, and feedwater pump. The reactor module in the primary loop is simplified as a heat source with 150 MW output. The steam generator that connects the primary and secondary loops is modeled with the heat exchanger module by transferring heat from helium to water/steam. Meanwhile, pressure and flow parameters can also be simulated for both helium and water/steam flows in steady-state and transient operating conditions. The steady-state simulation results are almost the same as the design data. The differences in the main steam temperature, feedwater pressure, and feedwater temperature, are 0.03%, 0.53%, and 0.02%, respectively. Meanwhile, the transient condition carried out in the loss of coolant accident showed a decrease in flowrate of 43.31 kg/s and an increase in temperature of feedwater and main-steam of 52.32 and 15.38 °C, respectively. In addition, there was a pressure drop of around 10.37 (feedwater) and 10.16 MPa (main-steam).

Could biomass-fueled boilers be operated at higher steam temperatures? Part 3: Initial analysis of costs and benefits

TAPPI Journal ◽  
2014 ◽  
Vol 13 (8) ◽  
pp. 65-78 ◽  
Author(s):  
W.B.A. (SANDY) SHARP ◽  
W.J. JIM FREDERICK ◽  
JAMES R. KEISER ◽  
DOUGLAS L. SINGBEIL
Keyword(s):  
Flue Gas ◽  
Power Plants ◽  
Superheated Steam ◽  
Black Liquor ◽  
Simulation Software ◽  
Operating Conditions ◽  
Costs And Benefits ◽  
Steam Generation ◽  
Fireside Corrosion ◽  
Corrosion Resistant

The efficiencies of biomass-fueled power plants are much lower than those of coal-fueled plants because they restrict their exit steam temperatures to inhibit fireside corrosion of superheater tubes. However, restricting the temperature of a given mass of steam produced by a biomass boiler decreases the amount of power that can be generated from this steam in the turbine generator. This paper examines the relationship between the temperature of superheated steam produced by a boiler and the quantity of power that it can generate. The thermodynamic basis for this relationship is presented, and the value of the additional power that could be generated by operating with higher superheated steam temperatures is estimated. Calculations are presented for five plants that produce both steam and power. Two are powered by black liquor recovery boilers and three by wood-fired boilers. Steam generation parameters for these plants were supplied by industrial partners. Calculations using thermodynamics-based plant simulation software show that the value of the increased power that could be generated in these units by increasing superheated steam temperatures 100°C above current operating conditions ranges between US$2,410,000 and US$11,180,000 per year. The costs and benefits of achieving higher superheated steam conditions in an individual boiler depend on local plant conditions and the price of power. However, the magnitude of the increased power that can be generated by increasing superheated steam temperatures is so great that it appears to justify the cost of corrosion-mitigation methods such as installing corrosion-resistant materials costing far more than current superheater alloys; redesigning biomassfueled boilers to remove the superheater from the flue gas path; or adding chemicals to remove corrosive constituents from the flue gas. The most economic pathways to higher steam temperatures will very likely involve combinations of these methods. Particularly attractive approaches include installing more corrosion-resistant alloys in the hottest superheater locations, and relocating the superheater from the flue gas path to an externally-fired location or to the loop seal of a circulating fluidized bed boiler.

scholarly journals CFD Simulation of Solid Suspension for a Liquid–Solid Industrial Stirred Reactor

2021 ◽  
Vol 11 (12) ◽  
pp. 5705
Author(s):  
Adrian Stuparu ◽  
Romeo Susan-Resiga ◽  
Alin Bosioc
Keyword(s):  
Chemical Reaction ◽  
Cfd Simulation ◽  
Simulation Analysis ◽  
Solid Phase ◽  
Initial Conditions ◽  
Chemical Reactor ◽  
Liquid Mixtures ◽  
Multiphase Model ◽  
Chemical Product ◽  
Two Phase

The present study examines the possibility of using an industrial stirred chemical reactor, originally employed for liquid–liquid mixtures, for operating with two-phase liquid–solid suspensions. It is critical when obtaining a high-quality chemical product that the solid phase remains suspended in the liquid phase long enough that the chemical reaction takes place. The impeller was designed for the preparation of a chemical product with a prescribed composition. The present study aims at finding, using a numerical simulation analysis, if the performance of the original impeller is suitable for obtaining a new chemical product with a different composition. The Eulerian multiphase model was employed along with the renormalization (RNG) k-ε turbulence model to simulate liquid–solid flow with a free surface in a stirred tank. A sliding-mesh approach was used to model the impeller rotation with the commercial CFD code, FLUENT. The results obtained underline that 25% to 40% of the solid phase is sedimented on the lower part of the reactor, depending on the initial conditions. It results that the impeller does not perform as needed; hence, the suspension time of the solid phase is not long enough for the chemical reaction to be properly completed.

A Nondimensional Analysis of Boiling Dry a Vertical Channel with a Uniform Heat Flux

1981 ◽  
Vol 103 (4) ◽  
pp. 667-672 ◽  
Author(s):  
K. H. Sun ◽  
R. B. Duffey ◽  
C. Lin
Keyword(s):  
Heat Flux ◽  
Nuclear Power ◽  
Closed Form Solution ◽  
Vertical Channel ◽  
Form Solution ◽  
Uniform Heat Flux ◽  
Two Phase ◽  
Drift Flux ◽  
Rod Bundle ◽  
Uniform Heat

A thermal-hydraulic model has been developed for describing the phenomenon of hydrodynamically-controlled dryout, or the boil-off phenomenon, in a vertical channel with a spatially-averaged or uniform heat flux. The use of the drift flux correlation for the void fraction profile, along with mass and energy balances for the system, leads to a dimensionless closed-form solution for the predictions of two-phase mixture levels and collapsed liquid levels. The physical significance of the governing dimensionless parameters are discussed. Comparisons with data from single-tube experiments, a 3 × 3 rod bundle experiment, and the Three Mile Island nuclear power plant show good agreement.

Sign in / Sign up

Export Citation Format

Share Document