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Plant Response Optimization BRINGING NUCLEAR QUALITY AND STANDARDS TO SYSTEM SIMULATION Flownex® is developed in an ISO 9001:2015 quality assurance system and NQA1 supplier approved environment. Flownex SE enables system level modelling of nuclear plant fluid mechanics, heat transfer and neutronic response in both transient and steady state. SIMULATION ENVIRONMENT www.flownex.com enquire@flownex.com +27 18 297 0326/7 NUCLEAR Cycle Design & Analysis Accident Scenario Evaluation DESIGN ANALYSIS TRAINING TYPICAL USES: System sizing. Component sizing. Determining operating ranges. Flow, temperature, pressure, power consumption, etc. Testing of control philosophy. Simulation. Performance assessment. Modification assessment. Fault root cause assessment. System behavior examination. Performing basic ow and heat transfer calculations. Thermohydraulic principles and properties referencing. NUCLEAR VERIFICATION AND VALIDATION A rigorous V&V process is followed in the development of those Flownex ® components relevant to the nuclear industry. These cases are captured in Flownex’s Verification and Validation pack which ensures their integrity for use in nuclear safety related applications. FLOWNEX ® LICENSE HOLDERS www.enginsoft.com [email protected] +33 (0)1 41 22 99 30
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Page 1: SMR Nuclear Brochure2018 Rev1 Spread - Powersys › wp-content › uploads › SMR... +33 (0)1 41 22 99 30 info.fr@enginsoft.com Integrated calculation of neutronic heat generation

Plant ResponseOptimization

BRINGING NUCLEARQUALITY AND STANDARDSTO SYSTEM SIMULATION

Flownex® is developed in anISO 9001:2015 quality assurance systemand NQA1 supplier approved environment.

Flownex SE enables system level modelling of nuclear plant fluid mechanics, heat transfer and neutronic response in both transient and steady state.

S I M U L A T I O N E N V I R O N M E N T

www.flownex.com [email protected]+27 18 297 0326/7

NUCLEAR

Cycle Design& Analysis

Accident ScenarioEvaluation

DESIGNANALYSIS TRAINING

TYPICAL USES:

System sizing.Component sizing.Determining operating ranges.Flow, temperature, pressure, power consumption, etc.Testing of control philosophy.

Simulation.Performance assessment.Modification assessment.Fault root cause assessment.

System behavior examination.Performing basic flow and heat transfer calculations.Thermohydraulic principles and properties referencing.

NUCLEAR VERIFICATION AND VALIDATIONA rigorous V&V process is followed in the development of those Flownex®

components relevant to the nuclear industry. These cases are captured in Flownex’s Verification and Validation pack which ensures their integrity for use in nuclear safety related applications.

FLOWNEX®

LICENSEHOLDERS

www.enginsoft.com [email protected]+33 (0)1 41 22 99 30

Page 2: SMR Nuclear Brochure2018 Rev1 Spread - Powersys › wp-content › uploads › SMR... +33 (0)1 41 22 99 30 info.fr@enginsoft.com Integrated calculation of neutronic heat generation

Integrated calculation of neutronic heat generation and pressure drop.

HTGR, PWR, MSR.Custom Specified reactor geometry.Vast selection of fluids and solid materials.Fuel moderator and coolant heat transfer and temperature results.

REACTOR MODEL

Relief valve sizingPassive heat removal analyses:

Natural circulationRadiative heat transferConjugate heat transfer

SAFETY ANALYSIS

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CYCLE & AUXILIARY SYSTEMS

Integrated plant transient response.Built-in DCS library.C# user scripting.MatLab/Simulink coupling.OPC coupling.

CONTROL PHILOSOPHY DEVELOPMENT

Engineering productivity for the design and analysis of complex thermofluid systems such as those found in large power plants is vastly improved by modeling in Flownex®. In addition, the system knowledge and understanding gained by the modeller is invaluable in subsequent activities.

Gary de Klerk, Pr. EngChief Engineer, Plant engineer Turbine Process Group TechnologyESKOM

Calculate temperatures, leak rates, pressure waves (water hammer) and pipe support loads for:

Loss of Cooling Accident (LOCA)Pump tripTube break in Steam Generator

ACCIDENT ANALYSES

Calculation of core flow and temperature distribution.Calculation of irradiation loop cooling and flow requirements.

RESEARCH OR MATERIALS TEST REACTORS

GAS & STEAM TURBINES Start-up, shut-down and load following operation.Turbine trip control.Gland steam systems.Lubrication systems.

BOILER STEAM SYSTEMSOnce-through and reheat boilers.Temperature calculation and change rates.Boiling stability & boiling regime examination.Detection of boiling oscillations (Ledinegg, density wave, pressure drop-type)Recirculation rate and steam production.Natural circulation boiler.Attemperation system.Dry out prediction.Load changes.

HEAT EXCHANGERSIntegrated heat exchanger components.Detailed heat tranfer components.User defined fluids as well as pressure drop andheat transfer correlations.FLOW CIRCUITS

Pipeline, valve and pump sizing.Water hammer.Cooling tower response.Heat exchanger sizing.Water reticulation flow balancing & energy efficiency.

Some Flownex Components for Nuclear Use

CONDENSERSWet and dry condenser heat exchange.Condenser level following.Air leak detection.

ActivePassive heat removal design.Neutronic specification options:

Built-in poin kenetics.C# user defined scripting.External software co-simulation.

SECONDARY CYCLE & AUXILIARY SYSTEMS MODELING


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