Focus on Technology AREVAs Thermal-Hydraulic Platform Content

Infrastructure and Technology • Thermal-Hydraulic Platform - Unique in the World • Infrastructure for Full-Scale Thermal-Hydraulic Test Facilities • Fluid-Dynamic and Thermal-Hydraulic Analysis • Similitude Tests, Optimization of Components and Processes • BENSON - Thermal-Hydraulic Separate Effect Tests • Vibrations and Mechanical Tests, Optimization of Power Plant Components • Seismic and Vibration Testing • Flow-Induced Vibration Tests, Optimization of Power Plant Components • Flow Model Tests, Optimization of Power Plant Components and Processes • Test Facilities for Power and Process Industry Applications

Integral Loops • INKA - Karlstein Integral Test Stand • PKL - PWR Integral System Test Facility

Qualification of Components • KOPRA - Component Test Facility, Qualification and Testing of Components at Full Scale • KOPRA - Core Component Test Section, Qualification of Primary-System Components • KOPRA - Test Section for Control Rod Drive Mechanisms • KOPRA - Valve Test Section • KOPRA - Special Valve Analyzing and Testing • KATHY Loop for Critical Heat Flux (CHF) Tests • PETER - PWR Fuel Element Tests at Erlangen • Fuel Assembly’s Components Testing • Reactor Steam Generator Component Testing • GAP The World’s largest Valve Test Facility • APPEL - AREVA Pump Test Loop • DEREST - Debris Retention System Test Facility • JAVAPlus Test Facility for Qualifying FCVSPlus • KADYSS - Test Facility for Qualifying Pump Seal System • Environmental Qualification of Containment Components • KATHAR - Test Facility for Qualifying Pressurizer Heaters

Services and Products • Valve Technology and Services, ADAM® Diagnostic System to Monitor Operational Availability • MDP - Mobile Torque Test Bench, Electrical Actuator Testing • RESI - Test System for Pressurizer Safety Valves • Classroom Training Course on PWR thermal-hydraulic system behaviour with PKL experimental results • Live Training Course at the PKL Test Facility • Steam Accumulator - Energy Storage for Thermal Processes • Unit Conversion Table - Conversion between International System of Units and British or US Sytem

Technical Center – Focus on Technology Technical Center - Focus on Technology

AREVA‘s Thermal-Hydraulic Platform Unique in the World

Facilities unique in the world for operating full- scale or scaled models for performing qualification tests of systems and components or for validating codes and calculations.

Scope of activities Resources • Qualifications: The thermal hydraulic and components testing - Pumps facilities comprise a total floor space of more - Valves than 2,000 m2 and heights of up to 32 meters. - I&C for loss-of-coolant accidents The following facilities are available: (LOCA) conditions • Crane capacities up to 100 t - Steam generator components • Thermal power supplies up to 25 MW - Auxiliary system components • Electrical power 20 MW • Systems tests: • Dose rate: 10-4 x limit for unrestricted release - PWR/BWR integral systems tests • Advanced measurement techniques also - Integral testing of sump strainer available and downstream systems We are qualified as a test and inspection body • Heat transfer and its limitations: within the following ranges: - For severe accident conditions - For core flow with focus on fuel elements Measurements Measuring Range - Heat exchangers Temperature 0 °C – 600 °C; 600 °C – 1,100 °C Pressure 7.5 Pa – 40 MPa 3 3 • Fluid dynamics and flow-induced vibrations Volume flow 0.0005 m /h – 100,000 m /h - Core flow and core components Mass flow 0.005 kg/h – 4,000 kg/s - Fuel assemblies Force 1 N – 10,000 kN - Singularities (T-junctions, etc.) Torque 1 Nm – 50,000 Nm Length 1 μm – 10 m • On-site activities Velocity 1 mm/s – 100 m/s - On-site measurements of NPP components Acceleration 0.05 g – 1,000 g - Generation of databases Current 1 μA – 85,000 A - Component inspections Voltage 1 mV – 4 kV Electrical power up to 20 MW Effective power up to 420 kW Weight 0.005 g – 3,000 kg Insulating resistance 50 kΩ – 200 TΩ (10 V – 1,090 V) Thermal-Hydraulic Platform Unique in the World

Test facilities • KATHY – Multifunction thermal-hydraulic test loop At our sites, we operate the following test facilities: • HYDRAVIB – Vibratory validation of lower • KOPRA – Multifunction component test facility RPV internals (fuel assemblies, CRDMs, valves) • ROMÉO & JULIETTE – RPV flow • BENSON – high pressure thermal-hydraulic distribution in upper and lower plenum testing of separate eff ects • CALVA – Dynamic mechanical testing of • PKL – Large scale test facility of a PWR primary components loop with secondary side and auxiliary systems • MAGALY – Vibration behavior of Rod • PETER, BRIAN – Fluid dynamic test facilities Cluster Control Assembly (RCCA) and (PWR and BWR fuel assemblies) Control Rod Guide Assembly (CRGA) for • SUSI – sump strainer test facility various flow conditions • APPEL – Pump test loop • Tri-axial seismic shake table – • GAP – Large valve test facility 3.3 m x 3.3 m table platform, flexible • INKA – Test facility for integral BWR tests mounting options for large equipment up to 9 tons

Your benefits at a glance • Highly qualified, experienced scientists, engineers and technicians • Knowledge base acquired over more than 40 years • Technical and economical solutions that make sense • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-127-V3-13-ENGPB Technical Center - Focus on Technology

Qualification of Components Infrastructure for full-scale thermal-hydraulic test facilities

Powerful and flexible infrastructure supplies full-scale test facilities with energy, high pressure steam, heat removal capability and demineralized water

The challenge The infrastructure offers: Large test facilities require a huge amount of steam • High-pressure steam-supply Benson boiler and electrical energy. An adequate infrastructure generates steam used for performing valve tests must be able to supply this energy flexibly and and LOCA qualification of safety-related reliably. The infrastructure must not only supply components and for supporting passive this energy, but also remove the energy that has safetysystem development. been added. A central water supply of treated and • 20 MW DC power supply has direct access to demineralized water is a prerequisite for operating the German grid and is used to perform critical such loops. heat flux tests using electrically heated fuel The solution assemblies for BWRs and PWRs. At the center of the component qualifi cation facility • Two heat removal systems is an infrastructure that can supply the various (High- and low-pressure) fullscale test loops with the required energy and • Water treatment plant supplies demineralized fluids with the required properties. water from two independent parallel lines.

Infrastructure • Benson boiler steam supply: 520 °C, 187 bar, 25 t/h • Electrical DC power supply: 20 MW, 83 kA • High-pressure heat removal system: 25 MW, 25 bar • Low-pressure heat removal system: 8 MW, 80 °C • Water treatment and demineralization plant: 2 x 6m3/h, < 0,2 μS/cm • Test section lines DN 150, 250 (8”, 10”)

The new Benson boiler is installed in the building Qualification of Components Infrastructure for full-scale thermal-hydraulic test facilities

Powerful and flexible infrastructure The infrastructure is constantly upgraded to meet new requirements. For example, in 2007, The powerful infrastructure allows erection and the DC power supply was upgraded from 15 operation of test facilities unique in the world, MW to 20 MW. in many cases at full scale. With this infrastructure supporting the test facilities, AREVA is able to qualify components such as feedwater supply and main steam isolation valves under full-scale conditions at mass flows of up to 4,000 kg/s.

Power upgrade from 15 MW to 20 MW 25 MW High pressure heat removal system

Your benefits at a glance

• Combination of powerful and flexible infrastructure and full-scale test facilities • Energy and fluid supply for test facilities unique in the world • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-110-V3-13-ENGPB Technical Center - Focus on Technology

Fluid-Dynamic and Thermal- Hydraulic Analysis

Full scope of analysis methods solves problems in the fields of fluid dynamics and thermal hydraulics

Solution orientation Program and physical model development Focused on solutions including: Specially developed, customized programs or • Describing or confi rming system or component physical models facilitate the solution of a task, function in our capacity as an accredited test enabling the customer to optimize his own and inspection body processes. The programs and models can be • Proposing component or system modifications based on databases from test results, or on one of • Developing correlations or models the following: • Developing databases in our capacity as an • Customized interfaces to OpenFOAM that employ accredited test body a user-friendly interface for performing, visualizing • Developing user-friendly test programs and interpreting calculations. The most appropriate process is chosen following • Development of 1-D codes, e.g., for two-phase analysis of the task, following the diagram below. flow network programs using correlations derived Numerical and analytical methods are crucial for from tests providing a direct solution or for supporting the • Physical model development, e.g., for CFD test related processes. programs. Our capabilities relevant to these goals are: • Performing numerical and analytical analyse • Developing physical models and related programs • Programming graphical user interfaces (GUI)

Numerical and analytical analyses Powerful computers are used together with highly efficient software to enable low-cost solutions for a wide variety of fluid-dynamic challenges: • 3-dimensional investigation of flow phenomena • Parameter studies of 3-D configurations with OpenFOAM, for example, pressure drop optimi- zation, heat transfer or efficiency parameters such as boundary layer separation • Flow optimization based on parameter studies • Analysis of thermal-hydraulic networks for pressure and heat loss, transient heating and cooling Velocity field within a heat recovery system downstream of a and mass-flow distributions gas turbine Fluid-Dynamic and Thermal-Hydraulic Analysis

Graphical user interfaces Software: User-friendly and intuitive data entry is a decided • CFD: OpenFOAM, CFX, Fluent advantage in handling complex calculation • 1D In-House Code: MultiFlow programs. • Interpreter: Mathematica, Matlab, Octave Features include: • Programming Languages: C# (.Net, Prism Pattern), C++, Fortran • Setting calculation parameters such as initial and boundary conditions Available customized programs • Preprocessing the input for the topology of • Thermal-hydraulic network for chemical thermal-hydraulic networks cleaning processes • Solver monitor: numerical parameter input and • Temperature and stress fields in boiler tubes calculational history tracking • Heat transfer, pressure drop, critcial mass flow in tubes • Solver and GUI for thermal-hydraulic boiler design programs

Solver GUI for the thermal-hydraulic network program

Thermal-hydraulic network topology Delivering the best solution for the customer defines the approach

Your benefits at a glance • High standards of quality provided by an experienced test and inspection body • Test results and analysis strongly linked • Best solution approaches identified from the problem definition • User-friendly program development based on test and analytical results • Special solutions developed based on OpenFOAM • Combined programming of calculation kernels/solvers and GUIs

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-143-V2-13-ENGPB Technical Center - Focus on Technology

Similitude Tests Optimization of components and processes

Fluid-dynamic and thermal-hydraulic tests validate and optimize design

The challenge In industrial plants, industrial processes and Test parameters industrial engines, complex system as well as individual components must be capable of • Mock-up scaling from 1:15 to 1:2 performing their designated function at all times • Water flow rates up to 850 kg/s during normal operation as well as under other, • Water temperatures up to 100 °C specific conditions • Pressures of up to 16 bar The solution • Lab floor area 1500 m² AREVA validates and optimizes component design using fluid-dynamic and thermal- Measured quantities and hydraulic tests. instrumentation • The first step in optimizing the tests and • Temperature costs is to identify the relevant physical • Pressure phenomena. The most relevant laws of • Flow rate similitude and non-dimensional numbers • Heat flux for designing the test are then defined. • Liquid density and viscosity • The second step is to define the scale of • Displacement (Laser vibrometer, the mock-up and the test fluid to reduce accelerometer, eddy-current sensors, the costs. strain gauges, displacement sensors) Numerical codes (EF, CFD) simulate component and system responses for Data acquisition nominal or accident conditions. However, • Powerful data acquisition and process experimental verification is still control systems (HBM, B&K, LabVIEW) indispensable for providing input data and validating code results.

Sedimentation of solid particles in a molten glass bed Gas-liquid interface in a tank under micro-gravity conditions Similitude Tests

Test experience Qualification of nuclear power plant components • EPR™ reactor pressure vessel pressure losses, flow mixing and flow-rate distribution • Thermal stratification and heat transfer in mixing areas • Jules Horowitz Reactor facility: flow-induced vibrations of reactor vessel internals • EPR™: flow-induced vibrations of the RPV internals Process engineering experiments • Sedimentation of particles in nuclear-waste vitrification EPR™ reactor pressure vessel mock-up: Juliette • Fuel tank optimization for ballistic phase of ARIANE 5 rocket

Experience in all fields of fluid mechanics EPR™ reactor pressure vessel mock-up: Romeo

Your benefits at a glance • Well-equipped laboratory using sophisticated measurement systems • More than thirty years of experience in testing and analysis • Applicable to nuclear and renewable energy projects • Integration with and access to AREVA’s thermal-hydraulic platform

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-168-V2-13-ENGPB Technical Center - Focus on Technology

AREVA’s Thermal-Hydraulic Separate Effect Tests / BENSON

Single-phase and two-phase flow applications investigated up to supercritical pressure conditions

The challenge • Guaranteed thermal performance data Investigating a wide variety of separate thermal • Pressure drop hydraulic effects, while achieving maximum • Natural circulation limits operational flexibility for single- and two-phase • Leakage rates operations at high temperature and high • Fouling pressure conditions up to supercritical pressure • Magnetite layer formation and behavior conditions With the test facility, AREVA investigates issues of power generation with fossil, nuclear and The solution renewable energy sources, as well as other AREVA operates a high-pressure test facility applications. whose flexibility and range of applications make it unique in the world. All kinds of test objects Our broad-based knowledge of all facets of water, can be installed in the facility and heated using water/steam and steam flows ensures that all a powerful direct-current power supply. A wide tests are proficiently performed. Over 40 years of variety of separate thermal-hydraulic eff ects experience in this field enable us to process the are investigated, such as: test results so that they are suitable for use either in directly clarifying separate eff ects issues or as • Heat transfer boundary conditions for numerical simulations. • Critical heat flux • Water/steam distribution

Flow diagram of high-pressure test facility High Pressure Test Facility / BENSON

Examples of power generation applications Reactor system thermal-hydraulics • Separate effect tests for condensers of new generation reactors • Heat transfer tests on a steam generator tube for fouling aspects (C.N.Trillo, Spain) • Investigations of fuel assembly cladding tube temperatures and pressure drop using a 5x5 rod bundle from a PWR • Studies of the TMI 2 accident • Verification of the cooling function in the EPR core melt spreading area • KERENA exterior vessel cooling concept safety margins Renewable energy applications • Investigation of heat transfer and flow behavior for direct solar steam generation by absorber/ evaporator tubes in CSP plants BENSON steam generators • Perform experimental investigations of heat transfer and pressure drop in vertical, inclined and horizontal smooth and rifled tubes heated either uniformly or on one side for BENSON licenses • Experimental results used to develop and validate the computer codes WATHUN and DRUBEN. These codes function as subroutines in boiler design programs in the fossil-fired power generation field. • Largest database in the world for CHF, heat transfer and pressure drop

Maximum flexibility in single- and two-phase Typical Test set-up flow applications

Your benefits at a glance • Test facility with maximum flexibility unique in the world • Applications for nuclear, fossil and renewable projects • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-142-V2-13-ENGPB Technical Center - Focus on Technology

Vibrations and Mechanical Tests Optimization of Power Plant Components

Separate fluid-dynamic and mechanical tests for nuclear power plants

The challenge In nuclear power plants, complex plant systems Test parameters and individual components must be capable of 3 • Flow rate up to 1000 m /h performing their designated functions at all times • Shaking devices with forces up to 2000 N during normal operation as well as under any • Temperature up to 100 °C postulated accident condition. Carefully designing • Pressure up to 16 bars and simulating the mechanical component response is possible using FE (finite element) Measurements and instrumentation codes, but to be truly dependable, the results of • Temperature, pressure, flow rate these codes must be validated. • Accelerometer, The solution • Displacement (Laser vibrometer, Mechanical and vibration tests on full-scale compo- accelerometer, Eddy current sensors, nent prototypes make the following possible: strain gauges, displacement sensor) • Providing input data about links and connections Data acquisition between the elements of a component • Powerful data acquisition and process • Validating the FE models and component control systems (HBM, B&K, LabVIEW) simulations • Assessing the manufacturing process

Fuel assembly instrumented with strain gages and displacement sensors on CALVA Bench

MAGALY bench: Flow-induced vibrations of control rod guide assembly and control rod cluster assembly Vibrations and Mechanical Tests

Test experience Qualification of nuclear power plant components

CALVA bench • Mechanical characterisation of EPR™ control rod guide assembly • EPR™ CRGA vibration fatigue tests, • EPR™ CRGA loss of function test • Mechanical characterisation and modal analysis of 14-ft fuel assembly

MAGALY bench • Flow-induced vibration of control rod cluster assembly for - EPR™ - 1300 MWe French plants

SOPHIE bench • Vibration behavior of steam generator tubes

SOPHI bench: vibration of steam generator tubes

Extensive experience in the nuclear power generation field

Your benefits at a glance • Well-equipped laboratory using sophisticated measurement systems • Applicable to nuclear and renewable energy projects • Integration with and access to AREVA’s thermal-hydraulic platform • More than thirty years of experience in testing and analysis

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-169-V2-13-ENGPB Technical Center - Focus on Technology

Seismic and Vibration Testing

One of the largest and most capable tri-axial seismic shake tables in the world. The generous 3.3 m x 3.3 m table platform offers flexible mounting options for large equipment, up to 9 t

Tri-axial seismic shake table

Description Specification

Types of waveform Time history earthquake (RRS-method), sinusoidal sweep, sine beat Table top size 3.3 x 3.3 m2 Maximum payload 9.000 kg Maximum frequency 100 Hz

Zero peak acceleration (ZPA) 7 g vertical (Z), 7 g longitudinal (X), 7 g lateral (Y) Peak spectral acceleration on 5 % response spectrum shall typically be 20 g

Peak dynamic displacement ± 125 mm vertical (Z), ± 125 mm longitudinal (X), ± 125 mm lateral (Y) under maximum load

Peak load 1.8 m/s vertical (Z), 1.8 m/s longitudinal (X), 1.8 m/s lateral (Y) Seismic and Vibration Testing

Safety is our number one priority! Customized test fixtures and analysis Customers communicate with the control room Our mechanical design team and in-house and witness test programs from the safety of machine shop provide customized rigid test the conference room overlooking the shake fixtures to ensure specimens are tested exactly table. Test specimens are received by truck as they are mounted in the field. Engineering through a large overhead door, and moved to support is available for finite element analysis the seismic shake table by a 5-ton overhead and resolution of test anomalies as necessary. crane. Data acquisition and testing support Calibrated data acquisition equipment includes accelerometers, chatter monitoring, and strain gauges depending on the application. The lab is equipped with high voltage AC/DC power supplies and other services allowing the operation and monitoring of test specimens during testing. Mechanical vibration testing and aging For smaller items weighing up to 150 kg, our single- axis electrodynamic shake table provides a mechanical and seismic testing capabilities, delivering 9 kN of sine force at velocities of 2 m/s.

Principle of the 6 dimensional shake table Qualification of valves, primary circuit internals, I&C equipment

Your benefits at a glance • Hydraulic and electro-dynamic shake tables • Full-service lab, supported by AREVA’s engineering capabilities and mechanical design • Quality assurance according to e.g.: Appendix B, NQA-1 and ISO approved quality program

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-302-V1-14-ENGPB Technical Center - Focus on Technology

Flow-Induced Vibration Tests Optimization of Power Plant Component

Integral hydraulic tests for power generation plants

The challenge Components in nuclear power plants must be Test parameters capable of withstanding flow-induced vibrations. • Water flow rate up to 3000 m3/h • Pressure up to 16 bars The solution • Temperature up to 100 °C AREVA validates and optimizes component design • Fluid velocity up to 20 m/s using flow-induced vibration tests. The relevant physical phenomena are analyzed and ranked. This Measurement techniques allows us to select the laws of similitude and non- • Laser vibrometer dimensional numbers in order to scale and design • Accelerometer an appropriate test rig model. The test rig model • Eddy current sensors represents the following physical phenomena: • Strain gauges • Significant flow-induced forces affecting the • Displacement sensor structure Data acquisition • Relevant structural responses and elasticities • Powerful data acquisition and process • Linkages between the various structures control systems (HBM, B&K, LabVIEW)

Jules Horowitz facility for flow-induced vibration of reactor internals.

HYDRAVIB: EPR™ test-rig model of reactor pressure vessel internals for flow-induced vibrations testing Flow-Induced Vibration Tests

Experience in testing Qualification of nuclear power plant components MAGALY bench • Control rod cluster assembly flow- induced vibrations for: – EPR™ – 1300 MWe French plants HYDRAVIB bench • Vibrations of EPR™ reactor pressure vessel internals RJH bench • Test bench at Jules Horowitz research reactor facility (RJH) – Vibrations of reactor internals

MAGALY bench: vibrations of control rod guide assembly and control rod cluster assembly

Experience in all fields of power generation

Your benefits at a glance • Well-equipped laboratories using sophisticated measurement systems • More than thirty years of experience in testing and analysis • Applicable to nuclear and renewable energy projects • Integration with and access to AREVA’s thermal-hydraulic platform

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-167-V2-13-ENGPB Technical Center - Focus on Technology

Flow Model Tests Optimization of Power Plant Components and Processes

Fluid-dynamic and thermal-hydraulic tests provided for all power generation fields

The challenge results to actual in-plant flow conditions, even when Whether power plants run on nuclear or fossil fuels the actual fluids in the plant are flue gas, steam or or on renewable energy sources, the complex plant oil. systems and individual components must be capable of performing their designated functions under normal and accident operating conditions. Capabilities and services of the Erlangen flow laboratory The solution • Fans providing air flows of up to 50,000 Nm³/h at 0.2 bar Flow model tests offer aid in the design process, design validation and optimization using • Compressor providing air flows of up to experimental rigs for the following: 2000 Nm³/h and 7.0 bar • Testing systems and components, for example, • Pumps providing liquid flows of up to during the design phase using reduced-scale 1000 m³/h and 10.0 bar models • Design and construction of flow models • Experimentally validating results of flow simulation • State-of-the-art instruments for measuring models generated with Computational Fluid pressure, velocity (LDA, hot wire probes), Dynamics (CFD) component vibration (LDV), concentrations (LIF, FID), temperatures and heat transfer The experimental setup must guarantee physical similarity of the modeled flow phenomena to the • Powerful data acquisition and process real flow conditions in the actual plant equipment. control systems (MERSY, LabVIEW) • Flow visualization using laser light-sheet To this end, fluids used for experiments are chosen techniques with simplicity and practical economics in mind, such as water and air. Applying appropriate similarity laws makes it possible to apply the experimental

Investigation of thermal mixing in PWR Simulation of swirling gas-turbine exit flow for studies related to heat-recovery steam generators Flow Model Tests

References Fluid dynamics experiments • KERENA safety concept: - Water/air experiments simulating the cooling of the exterior RPV for postulated core-melt accidents - Experiments investigating boron dilution in the reactor core (FABIS Project) • Experiments for NPPs, e.g., - Angra 1 (Brazil) - Brokdorf (Germany) - Stade (Germany) • Experiments for fossil-fired power plants, e.g., - Cottam (Great Britain) - Kansas City (USA) • SCR plants with PARMIX and TURBOMIX static mixers, e.g., - Brandon Shores (USA) - BASF (Germany) Process engineering experiments • Explosive limits of fuels for combined-cycle power plants (natural gas and coal gas) • Explosive limits of natural gas for gas distribution networks operated by the German utility Ruhrgas AG. Model used for optimizing a DeNOX reactor for a coal- fired power plant

Experience in all fields of power generation

Your benefits at a glance • Well-equipped laboratory with sophisticated measurement systems • Available for nuclear, fossil and renewable fuels projects • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-145-V2-13-ENGPB Technical Center - Focus on Technology

Test Facilities For Power and Process Industry Applications

Turnkey delivery specifically tailors design of test facilities for power and process industry applications to customer needs

Full scope of services • Experience communicating with authorities and expert organizations for jobs requiring conform- AREVA is qualified to deliver a full scope of test ance to national and international standards facility installation services according to customer • Expertise designing high pressure and demands. The full scope includes: temperature facilities for conditions up to • Project Management 300 bar and 1000 °C. • Planning • Design • Construction • Electrical installation • Data acquisition • Commissioning Design and construction benefits AREVA is highly qualified to design and construct test facilities because of our: • Experience in designing test facilities gained from modifying our own experimental rigs and from building several facilities for customers • Well-equipped workshops (elaborate welding technologies, 400 m² of workshop area, crane loads up to 100 tons) • Extensive knowledge in identifying and monitoring special vendors for non-standard components.

Rig for materials testing in corrosive environment Example of construction Test Facilities For Power and Process Industry Applications

Test facilities delivered ready-to-use This includes implementation of: • Measuring instruments • Automated process control equipment • Design and assembly of all electronic components • Data acquisition systems • Online visualization Powerful and cost-effective I&C implementation Because of our extensive experience in manufacturing and operating our own complex Fuel cell online process visualization test facilities, we always put the user’s needs in the foreground when programming the control systems. The user’s needs play an important part in designing user interfaces reduced to the bare essentials or in individually adapting process visualizations.

Data acquisition delivered ready-to-use • Graphical user interface • Automatic equipment protection • Adjustable data acquisition and recording intervals • Existing measurement devices simply triggered • Customer-specific user interfaces

Visualization of temperature profile

Your benefits at a glance • One-stop design and assembly of experimental rigs created according to customer specifications • Measurement and control systems appropriately selected • Standard parts employed or adapted cost-effectively • In-house programming assures optimal configuration of requested • Data acquisition system features high degree of interconnectivity • Process visualization customized for the specific application • Systems commissioned on-the-spot

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-140-V2-13-ENGPB Technical Center - Focus on Technology

Karlstein Integral Test Stand (INKA) Qualification of Components

Facility tests containment safety concepts under accident conditions, supports experimental analysis of specific scenarios and supplies data for code validation

The challenge Pool Vessel (FPV), the Drywell Vessel (DWV) and Numerical codes modeling system and containment the Pressure Suppression Pool Vessel (PSPV). The are often used to analyze accident scenarios specific design is derived from AREVA’s KERENA in light water reactors. These computer codes use reactor (3370 MW thermal). thermal-hydraulic correlations that are derived from The following components have been successfully active safety systems. With the use of passive tested: safety systems, however, the need to validate and • Emergency condenser to passively remove optimize these codes arises. energy from containment The solution • Containment cooling condenser to passively remove energy from containment The INKA test facility, more than 30 meters high, • Passive core flooding system was built by the Component Qualification Labora- • Fuel pool cooler tory to test and demonstrate the performance of the • Vent pipes passive safety systems of KERENA, an innovative • Passive pressure pulse transmitter boiling water reactor. Integral tests are performed to simulate transient INKA uses three vessels to represent the and loss-of-coolant accident (LOCA) scenarios. The containment of modern boiling water reactors: the powerful infrastructure of the Component Qualifica- Flooding tion Laboratory (e.g., the Benson boiler) supplies the test facility.

Technical data relative to KERENA: Scaling factors: • 1:24 in volume • 1:1 in height • 1:1 in component sizes Safety components: • Emergency condenser • Containment cooling condenser • Passive core flooding valve • Passive pressure pulse transmitter • Vent pipe, DN700 • Fuel pool cooler Vessels: • Flooding pool vessel, 210 m³ • Drywell vessel, 190 m³ • Flow rate: 200 kg/s (sat. steam at 85 bar) • Pressure suppression pool vessel, 350 m³ • RPV simulator, 125 m³

Karlstein integral test stand (INKA) Karlstein Integral Test Stand (INKA) Qualification of Components

Powerful and flexible The test facility is equipped with the versatile DAKAR data acquisition system for recording temperatures, pressures and vibrations, among others. In cooperation with research institutes from Germany and Switzerland, further measurements have been implemented using thermo pin probes, void fraction probes and mass spectrometry. Additional fields of application • Long term behaviour in accident scenarios • Heat transfer processes at water surfaces and stratification effects • Condensation processes in pipes, e.g. contain- ment cooling condensers and emergency condensers • Influence of non-condensible gases on heat transfer capacities (separate analysis of individual systems or long-term effects in accident scenarios) • Aerosol transport and deposition within containment • Interactions and influences of various systems, Test set-up active or passive, within the containment With its extensive Instrumentation (presently about 300 measurements can be recorded), Innovative features INKA is a unique test facility for simulating demonstrated by accident scenarios in containment and providing data to further improve system and containment full-scale tests modeling codes for all light water reactors.

Your benefits at a glance

• Only test facility of its kind in the world for containment scenarios • Experimental analysis of accident scenarios using active and passive safety components • Validation of system and containment codes • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-111-V3-13-ENGPB Technical Center - Focus on Technology

AREVA’s PWR Integral System Test Facility (PKL)

Model of a 4-loop PWR allows transient tests and parameter studies

Objective Design features AREVA’s PKL large-scale test facility allows us to The PKL test facility is scaled to simulate the conduct experiments on the thermal-hydraulic thermal-hydraulic system behaviour of a 1300 MW behaviour of PWRs during operational transients PWR plant: and accidents to achieve the following: • Heights are scaled 1:1 • To study overall system responses and system • Volumes and power are scaled 1:145 interactions • Primary/secondary pressure: 45/60 bar • To demonstrate safety margins and evaluate • The core is simulated with 314 electrically heated PWR operating procedures for design and rods, with original rod diameter and pitch, and pro- beyond-design-basis events vides power up to 10 % of nominal core power. • 4 steam generators, each featuring 28 tubes of Moreover, parameter studies and tests focusing on original geometry separate effects contribute to: • Supply of unique experimental data for thermal All primary and secondary operational and safety hydraulic system code development and systems are replicated: validation • Reactor coolant pumps (RCP) • Detailed understanding of complex PWR thermal- • Emergency core cooling systems HPSI, LPSI, hydraulic phenomena accumulators • Volume/chemical control system The PKL experiments contribute to solving PWR • Operational pressurizer spray system safety issues that T/H system codes cannot suf- • Main steam system ficiently represent. • Feedwater system, emergency feedwater system, feedwater preheater train

Main PKL design features • 4-loop configuration • Heights scaled 1:1 • Volumes scaled 1:145 • up to 10 % of nominal core power • max 45 bar of prim. pressure • max. 60 bar of sec. pressure All safety and operational systems of primary and secondary sides

PKL test facility Erlangen AREVA’s PWR Integral System Test Facility (PKL) System Testing

Unique and approved test facility The PKL facility is extensively instrumented, (over 1500 measuring points) permitting a detailed depiction of the phenomena addressed by the tests. The facility is particularly suited for detailed analyses and interpretation of complex phenomena difficult to assess with T/H system codes. More than 160 experiments covering a broad spectrum of scenarios have been addressed by Core simulator PKL experiments since 1977, many with inter- national cooperation via the OECD: • Large break/small break LOCA • Steam generator tube rupture • Main steam line breaks Core, top view • Station blackout, loss of feed water transients, bleed-and-feed procedures 1 Reactor Pressure Vessel • Systematic studies, e.g., single-/two-phase 2 Steam Generator natural circulation, reflux-condenser with/with- 3 Main Coolant Pump out non-condensable gases Upper plenum, 4 Pressurizer top view

Steam generators, top view Online process visualization

Your benefits at a glance • Only 4-loop experimental test facility of its kind in the world models PWR integral system behaviour • Transient and accident analyses, procedure validation and separate effect tests contribute to solving PWR safety issues.

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-139-V2-13-ENGPB Technical Center - Focus on Technology

Full Scale Tests with KOPRA Component Test Facility for Qualification and Testing

Extensive experience in qualifying components under operational conditions

Component qualification pressure test facility consisting of four test loops, three pressurizers and three Full-scale functional tests at appropriate circulation pumps for full-scale flow tests. temperature, pressure, and mass flow conditions are necessary for developing and qualifying nuclear components such as: Test parameters - valves - safety valves • Pressure up to 194 bar, - safety valve pilots • Temperature up to 360 °C - control rod drive mechanisms • Mass flows of water up to 400 kg/s, steam - fuel assemblies. up to 40 kg/s For endurance tests investigating long-term • Stationary/transient flow tests behaviour and wear effects, water chemistry must • Blowdown tests with one- or two-phases, be adjusted to mimic that of reactor coolant with and without subcooling conditions. • Adjustment of water chemistry Test facility (e.g., pH320 °C = 7.6) The KOPRA component test facility fulfills these requirements for PWR or BWR operating conditions. It is a multi-functional full-scale

KOPRA component test facility AREVA‘s Component Test Facility KOPRA Qualification and Testing of Components at Full Scale

Further resources • Access is available to other specialized work- shops and laboratories nearby: chemical and • Electrical and mechanical workshops manufac- material testing labs, calibration and EMC labs, ture standard products and special equipment. vibration laboratory, and instruments and tools • Extensive infrastructure includes state-of-the- center. art measuring systems, various power supplies and control equipment.

Component qualification testing laboratory in Erlangen

Your benefits at a glance • Combination of powerful and flexible infrastructure and full-scale test facilities • Integrated in AREVA’s thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-132-V2-13-ENGPB Technical Center - Focus on Technology

Core Component Test Section KOPRA Qualification of Primary-System Components

Fuel assemblies, rod cluster control assemblies and control rod drive mechanisms tested under operating conditions

Test facility design The fuel assembly (FA) is inserted in a fuel assembly channel between the lower support plate The KOPRA Core Component Test Section is (LSP) and the upper core plate (UCP). designed exclusively for full-scale tests on nuclear core components, matching coolant temperature, The control rod guide assembly (CRGA) is fixed in pressure and volumetric flow to the conditions in the place by the upper support plate (USP). pressurized water reactor. The test channel The test-channel vessel head matches the RPV contains a model of the central core position in the head configuration with its CRDM adaptor and RPV with complete geometry at a 1:1 scale. flange. The flow enters the test channel through the LSP, flows through the FA and the UCP and leaves the test channel via the openings in the lower support column of the CRGA at the same level as the hot legs of the RPV.

KOPRA core component test section simulating a PWR Instrumentation of CRDM during qualification test core position Core Component Test Section KOPRA Qualification of Primary-System Components

Fuel assembly testing • Functional tests of entire fuel assembly with simulation of LSP, UCP, USP, CRGA and operational flow conditions. • Investigations of fuel assembly and RCC-A behavior under normal and abnormal operating conditions. • Fuel assembly pressure drop measurements under operation conditions and wear measurements. • Endurance testing of flow-induced vibrations of fuel assemblies and fuel rods. • Special investigations for new designs, e.g., RCC-A insertion tests, fuel assembly floating tests.

CRDM testing • Functional tests verify adequate performance, e.g., latch-unit armature closing and opening times, mobile set effective weight, drive rod loads during stepping operation, RCC-A drop times. • Endurance tests to demonstrate that proper functioning can be reliably achieved over the specified number of CRDM steps and RCC-A drops with no damage. • Special investigations for new designs, e.g., velocity and vibration measurements of drive rod during stepping operation.

Test set-up CRDM qualification for EPRTM

Your benefits at a glance

• Designed for full-scale tests on nuclear core components at specific PWR flow, pressure and temperature conditions • Flexible test section for component qualification, endurance testing and functional testing • Accredited test and inspection body, accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-136-V3-13-ENGPB Technical Center - Focus on Technology

AREVAs Test Section for Control Rod Drive Mechanisms - KOPRA

Factory acceptance tests performed for all types of AREVA CRDMs used in PWRs

Test facility design The KOPRA CRDM Test Section is designed for qualification tests of control rod drive mechanisms (CRDM) under operational conditions. It consists of three test sections, a closed loop with circulation pump, heating and cooling systems, and a pressurizer. The CRDMs are mounted on flanges on top of the test sections and inside, the drive rods are con- nected to dummy weights simulating the RCC-A weights. For testing, the flow circuit heats the CRDMs to operating temperature. Stepping operation for the overall travel length and drops from the uppermost position are possible. At the end of the drop, a hydraulic damper slows the dummy weight. The CRDM test sections can be adapted to all CRDM types used in PWRs.

Test set-up for two AREVA CRDM types Set-up for CRDM factory acceptance test AREVAs Test Section for Control Rod Drive Mechanisms - KOPRA

CRDM testing • Hold the mobile set at any selected position along the travel length. After manufacture and assembly, every CRDM must be qualified under operational conditions. • Release the mobile set (for reactor trip). The first functional test phase under operational In addition, qualification can be performed conditions generates a magnetite layer on the of the complete CRDM as part of special sliding surfaces of the latch unit components, investigations for new designs, e.g., a rod ensuring optimal antifriction properties. This is position indicator system. the basic requirement for dependable CRDM latch unit functionality. For CRDM operation, various generations of PWR rod control systems are available, The qualification test ensures the three (such as contactor control, ELSTABE, operational functions of the CRDM: RodPilot® 10 and 40). • Insert and withdraw the mobile set (drive rod with coupled RCC-A dummy weight) in single steps to the required operating position.

Components of the CRDM RodPilot® 10 cabinet

Your benefits at a glance

• CRDM test section designed for FAT under operational conditions • Adaptation for all CRDM types used in PWRs • Various CRDM control systems available • Accredited test and inspection body, accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-133-V2-13-ENGPB Technical Center - Focus on Technology

Valve Test Section - KOPRA

Qualification tests for all types of valves in PWR and BWR systems up to DN 400 piping diameter

Test facility design Valve testing The KOPRA valve test section consists of a closed Valve testing and qualification at the KOPRA Valve circuit water loop of DN 150 with a circulation Test Section includes the following activities: pump, various test sections ranging from DN 15 • Performance tests for determining functional, to DN 150 (diagram item 1) and two pressurizers. material and loading behaviour and for trouble- Valves up to size DN 250 can be tested in this loop. shooting By combining the two pressurizers, tests with • Qualifying prototypes of all types of valves under temperature transients can be performed in the operational conditions to verify proper design closed water loop (1) and safety valve tests with • Generating data for valves relevant to safety and one- or two-phase flow using a silencer (diagram operation. These data represent a baseline item 2) are possible. A valve test array (diagram measurement for the ADAM® valve diagnostic item 3) accommodates the pilot valve in-service hot system and form a reference for future in-service adjustment test with steam. tests A second closed-circuit water loop is available • Performing functional and setting tests for safety within the KOPRA facility for testing valves up to valves by simulating operational transients DN 400. • In-service hot adjustments for safety valve pilots

• Determining flow coefficients (Kv value) of valves up to DN 100 in a separate cold-water test section

Valve test section KOPRA Valve Test Section - KOPRA

1 Closed water loop for valve testing

2 Functional test of a safety valve under operational 3 Test set-up for hot adjustment of pilot valves on and accident conditions the valve test array

Your benefits at a glance

• Testing under operational conditions • Water flow up to 400 kg/s, steam flow up to 40 kg/s • Stationary/transient circulation tests • Blowdown tests with one- or two-phases, with and without subcooling • Accredited test and inspection body, accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-134-V2-13-ENGPB Technical Center - Focus on Technology

Special Valve Analysis & Testing KOPRA

Facility qualifies and functionally tests valves with diameters ≥ DN 200 under simulated operating conditions

Test facility design With a possible test-section length of 4.7 meters, the test circuit allows valves with nominal A newly developed special valve analysis and diameters from DN 200 to DN 500 to be installed testing (SVAT) circuit within the KOPRA Core in-line using transition pieces. DN 200 PN 250 Component Test Facility allows testing valves for flanges in the test circuit provide the connections nuclear applications under simulated operating to the test section. conditions. Coolant temperature, pressure and volumetric flow are matched to reactor conditions. The open test-section length can be isolated using Connecting piping has a nominal diameter of DN two gate valves. This facilitates uncomplicated 200.. test-section modifi cations, such as changing flow direction. With a maximum volumetric flow capacity in the test circuit of 1400 m3/h, flow velocities of 5 m/s Circulation and higher are possible (see graph below). pump Continuous adjustment of the volumetric flow is available. A bypass system facilitates endurance tests involving the full range of valve motion from open to closed. Flow measurements upstream of the test section can confirm that the flow capacity of the valve Bypass being tested meets requirements, up to the test Flow circuit’s 1400 m3/h flow capacity. Adjusting the feedwater properties to mimic operational conditions, including the addition of chemicals such as LiOH or boric acid, is possible.

Gate Valve

Theoretical maximum Flow Velocity gate valves at V = 1400 m3/h and 20 °C/160 bar

Flow velocity at full open

Flow velocity at half open

Gate Valve Flow velocityFlow [m/s]

4.7m: test-section length Nominal Diameter [DN]

KOPRA – SVAT circuit Flow velocities possible in the SVAT circuit Special Valve Analysis & Testing KOPRA

Valve testing • Flow velocities of up to 5 m/s or more • Functional testing of valves at simulated • Endurance testing for flow-induced vibrations operational flow conditions • Special investigation and analysis of new designs (e.g., thermal shock tests) • Endurance testing of valves under operational conditions Test parameters and capabilities • Pressure up to 175 bar • Volumetric flow of up to 1400 m3/h • Test-section installation length of 4.7 m • Tests for gate and angle valves, among others • Nominal diameters DN 200 to DN 500 • Flange connections to the test circuit • No weight limit for valves because of test circuit’s basement location

Instrumented test specimen SVAT test-circuit setup for thermal shock testing

Your benefits at a glance

• Tests of nuclear components under full-scale temperature and pressure conditions at high volumetric flow • Flexible test circuit for valve qualification, endurance and functional testing • Accredited test and inspection body, accepted by ILAC and open to external costumers

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-283-V1-14-ENGPB Technical Center - Focus on Technology

Critical Heat Flux (CHF) Tests with AREVAs KATHY Loop

CHF tests are essential for licensing nuclear fuel. The KATHY-Loop is designed to determine the CHF under large-scale. The KATHY Loop determines CHF under large scale conditions with electrically heated fuel assembly models

The challenge perature and mass flow, are kept constant during the CHF test performance while the power is CHF testing with electrically heated fuel assemblies slowly increased until CHF is reached. is a challenging task. Large amounts of electric power has to be precisely handled and quickly The extensive thermocouple instrumentation controlled when CHF occurs. Determining the onset inside the heated rods allows determination of the of CHF requires sophisticated and robust measure- axial and radial appearance of CHF inside the test ment technology operating under high pressure and bundle. temperature. The main components of the KATHY-Loop are: The solution • 20 MW electrical DC-supply The multifunction “Karlstein thermal-hydraulic test • Two test vessels housing the test bundles loop” KATHY is designed to determine the onset • Direct-contact cooling condenser of CHF in electrically heated rod bundles that are • Broad range of measurement systems geometrically identical to real fuel assemblies. The KATHY Loop operates at full-scale geometry. The • Control valves and systems thermal-hydraulic conditions such as pressure, tem- • High- and low-pressure heat removal system

Characteristics of KATHY-Loop • Electrical DC power: 20 MW, 83 kA • Design pressure: 185 bar • Design temperature: 360 °C • Flow rate: max 250 m³/h • Precise, automated power control system • 620 data channels (easily extendable) • Test bundle geometries: 5 x 5, 9 x 9, 10 x 10, 11 x 11, 12 x 12 • Axial power profiles: cosine, top-peak, down-peak, uniform

Karlstein thermal-hydraulic test loop KATHY Qualification of Components KATHY Loop for Critical Heat Flux (CHF) Tests

Versatile and multifunctional test loop • Single-phase pressure drop measurements performs • Adiabatic two-phase flow pressure drop measurements. • CHF tests on full-scale BWR test bundles • Void fraction measurement with gamma ray • CHF tests on 5x5 PWR test bundles densitometer • Simulation of reactor transients (e.g., pump trip, turbine trip) • Hydraulic stability investigations on BWR test bundles under natural circulation conditions • In operation since 1986 with more than 30,000 test runs.

Experienced in CHF since 1986 and well equipped for the future.

Installation of a test bundle A test bundle has the same geometry as a fuel assembly

Your benefits at a glance • State-of-the-art test loop • More than 2,500 heater rods in stock • Duration of each test step: 5-10 min. • Benchmarked against OMEGA-Loop (CEA), ATLAS-Loop (GE) and HTRF- Loop (CU) • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-112-V3-13-ENGPB Technical Center - Focus on Technology

PWR Fuel Element Tests at Erlangen PETER

Full scale thermal-hydraulic facility tests PWR fuel assemblies for FA vibration and bowing behavior under various geometric and flow boundary conditions

The challenge Measurement techniques Reliable and safe FA operation at maximum Today, laser-based techniques measure the main performance promotes optimal NPP operation. FA characteristics as follows: This must be ensured for a wide variety of FA • Laser triangulation measures vibration behavior designs in combination with a number of different of the FA structure plant designs. • Laser vibrometer quantifies fuel rod vibration behavior The solution • Laser triangulation measures static movement of Operating a test facility with maximum flexibility the entire FA in geometric and flow boundary conditions. • Laser-doppler velocimetry quantifies the flow Experimental investigations of PWR fuel velocity distribution between fuel rods assemblies enhance nuclear power plant safety and reliability. Optimizing fluid-dynamics performance leads to new developments in fuel assembly design and helps improve plant economics, for example: • Better coolant mixing enables achievement of higher power levels and higher burn-ups, improving economic efficiency • The in-core reliability of AREVA fuel assemblies can be enhanced even further • Fuel assembly costs can be optimized

Laser measurement in PETER test facility Measurements of stiff ness behavior of fuel elements dependent on flow conditions

PWR Fuel Element Test Facility / PETER

Applications • Vibration and bowing behavior of fuel elements • Influence of neighboring fuel elements on mechanical behavior of fuel element – Neighboring fuel element of different design – Pre-shaped neighboring fuel element (C or S bow) • Influence of specific geometric boundary conditions (fuel element position at core shroud, edge or line position) • Influence of cross-flow on mechanical behavior of fuel element • Sensitivity studies of spacer design on mechanical behavior of fuel element • Pressure drop measurements for developing new fuel assembly spacer designs or for optimizing fuel assembly geometries.

PETER loop test set-up

Safe and reliable FA operation at maximum performance

Your benefits at a glance

• Test facility with maximum flexibility unique in the world • Applicable to all designs of PWR fuel assemblies • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-146-V2-13-ENGPB Technical Center - Focus on Technology

Fuel Assembly’s Components Testing Design Validation and Life Time Assessment of FA Elements

Comprehensive testing and competencies to support the hydraulic and mechanical design validation, mechanical properties and the life time justification of fuel assembly’s components

The challenge AURORE and FANI test benches In nuclear power plants, fuel assembly must • Sliding, impact, impact-sliding, fretting withstand solicitations like hydraulic forces, wear, • Force up to 240 N, vibrations and fretting in normal operation, dynamic water environment, 320 °C and 154 bar loads during abnormal situations like earthquake or Wear on fuel rod cladding or thimble tubes LOCA. CALVA test bench We propose a wide variety of test facilities and • Mechanical and vibration tests on full scale fuel competencies applied to hydraulics, mechanics assembly in air or wear. Tests are related to design qualifi- Fuel assembly vibration modes, axial and cation, mechanical properties characterization lateral stiff ness, strains on thimble tubes and life time justification and provide input data for hydraulic and mechanical calculations. Dynamic crush test bench • Impact speed up to 1 m/s Test facilities • Temperature up to 320 °C Loops 1000 & 3000 Grid/fuel bundle slip load, grid lateral stiffness • Water flow up to 800 kg/s • Temperature up to 110 °C Delphine II bench • Fuel rod insertion speed up to 15 m/min Pressure drop coefficient and hydraulic lift force applied on grids, top or bottom nozzles Friction loads during fuel rod insertion in the fuel assembly skeleton

Dynamic crush bench for fuel assembly grids

CALVA Bench: Full scale fuel assembly instrumented with strain gages and displacement sensors

Fuel Assembly’s Components Testing

Our scope of services • Characterisation of wear mechanisms • Direct measure of hydraulic lift forces on grids, top or bottom nozzles • Measure of pressure drop coefficients at real reactor Reynolds number • Vibration modes, stiff ness and mechanical characteristics measured on full scale fuel assemby prototype Delphine II test bench • Unique dynamic crush test bench for grid lateral stiffness measure • Unique Aurore and Fani benches to measure friction and wear between fuel rod clad and grid cell elements like spring or dimple Professional consulting • Instrumentation of each apparatus (force, and services in hydraulics, displacement, pressure, temperature, mechanics and vibrations vibrations) in a single skilled team • Development of specific software to pilote benches and to perform data acquisition • Signal and data processing (friction coefficient, wear rate, …)

Your benefits at a glance

• Well equipped laboratory with sophisticated benches and measurement systems • More than twenty years of experience and analysis • Short reaction times even for complex tasks • Readily available laboratory infrastructure in associated disciplines • Hydraulic, mechanical and vibratory skills from one single source

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-231-V1-13-ENGPB Technical Center - Focus on Technology

Steam Generator Component Testing Design Validation and Life Time Assessment of SG Elements

Comprehensive testing and competencies to support the hydraulic and mechanical design validation and the life time justification of reactor steam generators components

The challenge AURORE test benches In nuclear power plants, steam generator (SG) and • Sliding, impact, impact-sliding, fretting SG components must withstand solicitations like • Force up to 240 N, hydraulic forces, flow induced vibrations, fretting steam environment up to 320 °C and wear in normal operation, dynamic loads and and up to 154 bar displacements during abnormal situations like earthquake or LOCA. Wear on steam generator tubes and anti vibration bars We propose a wide variety of test facilities and competencies applied to hydraulics, mechanics SOPHIE test benches or vibrations and wear. Tests are related to • Mechanical and vibration tests on SG tubes and design qualification, mechanical properties repaired SG tubes in air. SG tube vibration characterization and life time justification and modes, wear of SG tube/stabilization devices, provide input data for hydraulic and mechanical assessment of tube-tube and tube-support calculations. plate junctions.

The facilities SG support plate compression test bench Steam generator dryer drains mock-up • Quasi static compression test of a full scale half • Reduced scale mock-up of SG dryers and drains support plate. Support plate and local cells • Air & simulating fluid (instead hot steam & water) deformation vs load Maximum flow rate in drain per stage of dryer

Steam generator dryer drains mock-up Steam generator support plate compression test bench: deformation of SG support plate and cells under continuous compression load

Reactor Steam Generator Component Testing

Our scope of services • Characterisation of wear mechanisms,

• Unique skills and knowledge to design, manufacture and operate test facilities in hydraulics and mechanics

• Vibration modes and mechanical characteristics measured on full scale SG tubes

• Unique Aurore to measure wear between SG tube and Anti Vibration Bar

• Instrumentation of each apparatus (force, displacement, pressure, temperature, vibrations)

• Development of specific software to pilote benches and to perform data acquisition

• Signal and data processing (friction coefficient, wear rate,…) Sophie test bench: vibrations of steam generator tubes

Professional consulting and services in hydraulics, mechanics and vibrations in a single skilled team

Your benefits at a glance

• Well equipped laboratory with sophisticated benches and measurement systems • More than twenty years of experience and analysis • Short reaction times even for complex tasks • Readily available laboratory infrastructure in associated disciplines • Hydraulic, mechanical and vibratory skills from one single source

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” Technical Center - Focus on Technology

The World’s Largest Valve Test Facility GAP / Qualification of Components

Valve testing under full-flow conditions with more than 40 years of experience

The challenge The facilities can be operated with cold, sub- cooled, saturated water as well as saturated and The functional capability of safety-related valves superheated steam. Phase transitions are also must be verified by both analytical and possible (e.g., steam to two-phase or steam to experimental qualification. However, analytical water). verification is not always possible to the extent required, particularly in the case of new designs. Numerical tools are available to forecast and support the course of the test based on test valve The solution flow characteristics. Large-scale valve test facilities operated in Several valve test facilities are available. The two Karlstein by the component qualification laboratory most relevant are the Large Valve Test Facility are able to simulate operational and accident (GAP) and the High Pressure Test Facility (VPE). conditions. The component qualification infrastructure also The facilities are used for qualifi cation, prototype, provides test capabilities beyond the design data functional and factory-acceptance tests. mentioned below, such as valve tests with water at 300 bar and 50 t/h.

Technical data: Large valve test facility (GAP): • Design pressures up to 165 bar • Design temperatures up to 350°C • Total flow rate up to 2,000 kg/s (steam), 4,000 kg/s (two-phase), 1,300 kg/s (water) • Accumulator volume 125 m³ • Test section lines DN 250, 400, 700 (10”, 16”, 28”) High pressure test facility (VPE): • Design pressure 157 bar • Design temperature 400 °C • Flow rate: 200 kg/s (sat. steam at 85 bar) • Accumulator volume 22 m³ • Test section lines DN 150, 250 (8”, 10”)

Large valve test facility (GAP) The World’s Largest Valve Test Facility GAP Qualification of Components

Powerful, versatile and full-scale • Pressurizer safety relief valves, including under ATWS conditions Over the past 40 years, the following valves have been successfully tested: • 3-way valves, check valves and many others • Main steam isolation valves up 30” Tests can be performed in accordance with (e.g. globe and gate) international standards, such as ASME QME-1. • Feedwater isolation valves up to 10” Static loads can also be applied under full flow. (e.g. globe and gate) • Setpoint verification and flow capacity tests on safety valves (spring-loaded, self- or pilot- actuated)

Large valve test facility …. Full flow ….

Your benefits at a glance

• Full-scale valve testing • 40 years experience in valve testing • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-109-V3-13-ENGPB Technical Center - Focus on Technology

AREVAs Pump Test Loop APPEL

Pumps qualified in accordance with ISO 9906 and at accident operation conditions such as fast thermal transients or particle-loaded water

The challenge be taken into account. Endurance tests must also be performed. The APPEL facility allows maximum Qualifying pumps at standard conditions described flexibility in performing the requested in ISO 9906 as well as for accident conditions such qualifications. as fast thermal transients or for operation with particle-loaded water following a LOCA Typical measurements define:

The solution • Flow rate • System pressure Setting up a test facility able to perform standard • Pump discharge head pump performance tests in accordance with • Vibration behavior of pump and motor ISO 9906 as well as special tests without changing • Fluid temperature loop components. For pumps operating in nuclear • Temperature of pump and motor components power plants, qualification at the standard • Motor power conditions defined in ISO 9906 is often insufficient. • Pump rotation frequency Specific conditions such as thermal transients or pump operation with particle-loaded water must.

APPEL pump test facility

AREVAs Pump Test Loop APPEL

During pump operation under fast thermal transient conditions, the pump can undergo a APPEL test facility specifications: thermal shock due to as much as a 165 K temperature change in less than 30 s. The • Test facility material: shocks can be applied from cold to hot or even Stainless steel hot to cold conditions. Pump endurance tests • Max. pump suction pressure: are performed at elevated temperatures for 40 bar several hundred hours, combined with frequent • Max. pump discharge pressure: on/off pump switching operation. Qualification 100 bar for pump operation with particle-loaded water can also be performed over a long term. • Max. system temperature: AREVA supplies and prepares the debris 200 °C mixture. • Max. flowrate: 1000 m³/h APPEL applications • Max. drive power: 450 kW Qualification tests have been performed for:

• Standard chemical pumps (EN 9906) Test facility specifications • Single stage/multi-stage vertical pumps (EN 9906) • LHSI pumps for EPR™ (EN 9906, thermal transient and debris tests) • EVU pumps for EPR™ (EN 9906, thermal One pump test facility to transient and debris tests) satisfy all your needs • LHSI pumps for other NPPs (EN 9906, thermal transient and debris tests)

Your benefits at a glance

• Pump test facility with maximum flexibility combines standard EN 9906 application and special tests • Integration with and access to AREVAs thermal-hydraulic platform • Accredited test and inspection body in accordance with ISO 17025 and 17020

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-141-V2-13-ENGPB Technical Center - Focus on Technology

Debris Retention System Test Facility DEREST

Qualification of debris retention system performance accounts for pressure loss, chemical effects and downstream effects

The challenge • the ability to backflush the sump strainers Qualification of debris retention systems designed • pressure loss caused by debris bypassing the to protect SIS pumps and core components from sump strainer (downstream eff ects e.g., on FA) clogging in case of a LOCA. • influence of erosion and corrosion (chemical processes) on pressure loss The solution The best way to investigate all these topics The facility is designed to investigate the effects of simultaneously is with an integral test facility. The debris-releasing processes that follow a loss-of two main issues of deposition on strainers and coolant accident (LOCA) in the reactor sump downstream effects can be covered. region and downstream of the sump strainers. The following parameters are considered: The integral test facility consists of: • debris transport and sedimentation in the reactor • Leak region sump; • Test flume • pressure loss caused by debris agglomeration on the sump strainer; • Recirculation pump • influence of strainer geometry and size of the • Fuel assembly test rig strainer openings on the pressure loss; • Debris preparation pool

Break simulation Fuel assembly test rig

Water storage tank

Test flume Main Pump Debris preparation pool

DEREST test facility

Debris Retention System Test Facility DEREST

Flexible test facility The composition of the debris material and its injection sequence are adapted to the specific The flexible set-up of the facility handles all break scenario. Chemical effects such as boric kinds of strainer designs. The leak simulation acid or chemical substances added or is designed according to the plant-specific produced in the long term post-LOCA phase situation. The vertical 1:1 scaling correctly can be taken into account. simulates the energy dispersion of the water

falling from the leak. DEREST applications Test duration varies from short term tests Qualification tests have been performed for lasting several hours, to long term tests lasting • all German PWR NPPs up to 30 days. • all EPR debris retention system designs

DEREST facility specifications • Strainer design: all types • Water volume: 25 m³ • Max. flowrate: 50 kg/s • Debris load: variable • Debris type: all types • Temperature: 80 °C max. • FA section: included • Chemical effects: available • Downstream effects: available

DEREST facility specifications

Integral test facility qualifies all debris retention system

DEREST downstream fuel assembly test section designs

Your benefits at a glance • Test facility with maximum flexibility accommodates all designs • Integration with and access to AREVAs thermal-hydraulic platform • Accredited test and inspection body

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-144-V2-13-ENGPB Technical Center - Focus on Technology

JAVAPlus Test Facility for Qualifying FCVSPlus

Filtered containment venting efficiently retains organic iodine

The challenge The main components of JAVA Plus are: During a severe accident, the pressure inside • 1st filtration stage: high speed venturi section containment might surpass the containment design retains signifi cant quantities of iodine and most pressure. To ensure containment integrity, the aerosols. The ability to flush the scrubbing liquid containment must be depressurized by venting. back to the containment following the venting The vented gas must be filtered to the fullest sequence significantly decreases the activity extent possible to reduce the activity release to the inside the filter. environment. At the same time, the venting system • 2nd filtration stage: the metal fiber filter retains must be operable under all conceivable conditions residual droplets and aerosols, including hard-to- and function passively, that is, without electrical retain fine aerosols. power. • 3rd filtration stage: This new passive superheating and sorbents section retains The solution elemental and organic iodine. AREVA has developed the filtered containment venting system (FCVS), comprising a venturi scrubber and a metal fiber filter section. This Characteristics of JAVA Plus system retains aerosols and elemental iodine with • Design data: high efficiency. Recent research, such as the Pressure: 10 bar PHEBUS tests, indicates that organic iodine Temperature: 200 °C (CH3I) also carries significant amounts of activity during severe accidents. This substance, Volume: 8000 l therefore, must also be filtered out. The new Test media: steam, air Plus FCVS is an innovative extension of the existing Mass flow: up to 2 kg/s (steam & air) FCVS. It adds a passive superheating module and High and low pressure / temperature operation a molecular sieve (I-CATCH). As a result, the retention of organic and elemental iodine is signifi- Modular design: sorbents stage cantly increased. scrubber stage • Decontamination factors (DF): For aerosols: – Fine aerosols > 10.000 – Large aerosols > 100.000 For iodine: – Aerosol iodine: > 3.000.000 Under verification: – Elemental iodine > 1000 – Organic iodine > 50 • State-of-the-art data acquisition

Filtered Containment Venting System Plus

JAVAPlus / Qualification of Components

Versatile and multifunctional test • Operation of large scale test facility: facility features – Prototype equipment • Testing filtered containment venting system – Full height as original vessel FCVSPlus for various reactor types: PWR, – Mass flow scaled to 1/5 of real venting BWR, PHWR, CANDU and VVER. system • Testing performance with various steam-to- air ratios.

JAVA Plus test facility in operation

FCVSPlus filters a greater number of radioactive species from containment gas vented during severe

JAVA Plus test facility accident mitigation

Your benefits at a glance • Representative results obtained by operating large-scale test facility (no penalties for laboratory effects) • Organic iodine (CH3I) retention tests • Participation in the European Union PASSAM program • Integration and access to AREVAs thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-284-V1-14-ENGPB Technical Center - Focus on Technology

Test Facility for Qualifying Pump Seal System / KADYSS

Facility simulates effects of station blackout on pump-shaft seal systems in nuclear power plants

The challenge The heart of KADYSS is a shaft-displacement system developed to realize very precise axial Simulating station blackout (SBO) conditions in a movements at very low velocities. KADYSS is long-duration test of the circulation pump-shaft equipped with extensive instrumentation for seal requires feedwater at PWR conditions to pressure, temperature and mass flow. compensate for the leakage flow of the sealing system. Mimicking the shaft’s thermal expansion The main components of KADYSS are: due to the internal thermal transients requires precise control of the shaft displacement. • Electrically heated pressurizer • Cold-water injection pump The solution • Test vessel The KArlstein DYnamic Shaft Seal test facility - simulates the connection to the primary loop simulates the effect of SBOs on the shaft-seal • Pressure and temperature control systems systems of nuclear power plant (NPP) circulation • Precisely controlled shaft displacement pumps. The facility operates under full PWR • High-pressure filter system conditions. Thermal-hydraulic conditions such as pressure and temperature are kept stable while the • Data acquisition system Karlstein infrastructure compensates for the leakage flow of the shaft-seal system.

Actuator Characteristics of KADYSS Throttle • Design data: leak-off line Seal Pressure: 185 bar leak-off line Temperature: 360 °C Leakage flow: < 1000 l/h • Shaft displacement system: Total movement: 3.0 mm Housing Velocity: 0.05 to 10 mm/h Design load: 33 kN • Pressure and temperature control system • Modern data aquisition Auxiliary line • Qualification of different types of sealing Injection principles line Shaft

KArlstein DYnamic Shaft Seal test facility KADYSS

Qualification of Components / KADYSS

Versatile and multifunctional test loop • Tests under simulated accident conditions up to 185 bar and 360 °C. • Performs SBO tests on shaft seal systems of different types of circulation pumps and • Tests pressure and temperature transients different types of sealing principles. and precise axial shaft displacements.

Instrumented specimen connected to leak-off lines

KADYSS puts your seal system under pressure

KADYSS in operation

Your benefits at a glance

• Testing under full scale test conditions • Long duration tests • Integration with and access to AREVAs thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-285-V1-14-ENGPB Technical Center - Focus on Technology

Environmental Qualification of Containment Components

Environmental qualifications performed in accordance with international standards (e.g., KTA, IEEE, RCC, US NRC 10CFR50 Appendix B)

The challenge This includes preparing and planning in close cooperation with the customer as well as Environmental qualification tests must be performing all tests. performed on safety-related components that are required to operate under accident and post- The available test facilities include: accident conditions, such as for a loss-of-coolant Preconditioning (aging): accident (LOCA). Proper function must be verified throughout the lifetime of the component. • Heating chamber – Test volume: 5.9 m³ The solution – Design temperature: to 180°C The AREVA component qualification laboratory • Climatic chamber offers a full range of services to meet the – Test volume: 1 m³ requirements of a qualification campaign. – Design temperature: - 40 °C to 180 °C – Design humidity: to 98 % • Radiation-aging and vibration tests are performed in cooperation with our partner laboratories.

Environmental qualification • Preparation of procedures and test campaigns in cooperation with our customers • Performance of qualification tests: - Climatic test - Thermal aging - Radiological aging - Vibration tests - LOCA / SA tests - Accidental radiation - POST LOCA tests • Handling of the test specimens and preparation of auxiliary systems • Planning and supply of customized measurement equipment

Heating and climatic chamber Qualification of Components Environmental Qualification of Containment Components

Simulation of accident conditions • POST LOCA test chamber VB2600 Accident simulation - Test volume: 2.6 m³ - Design conditions: 100 °C / 1 bar (abs) • LOCA test chamber - Chemical solution spray system - Test volume: up to 5.4 m³ • POST LOCA test chamber VB12000 - Design conditions: 250 °C / 10 bar (abs) - Test conditions: saturated / superheated - Test volume: 12 m³ steam - Design conditions: 168 °C / 6 bar (abs) - Injection time: 10–15 s (from 25 °C–160 °C) - Chemical solution spray system - Chemical solution spray system

I

POST LOCA test chamber VB2600 LOCA test chamber

Your benefits at a glance • Many years of experience – about 500 environmental qualification campaigns in the past 25 years • Integration with and access to AREVAs thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-113-V3-13-ENGPB Technical Center - Focus on Technology

AREVAs Test Facility for Qualifying Pressurizer Heaters / KATHAR

Long-term behavior of pressurizer heaters determined under full pressure and temperature conditions with simulated service life

The challenge The main components of the test facility are: Qualifying newly designed heaters requires • Test vessel simulating service life (electrical loading) at design • Heat removal system pressure and temperature. The challenge is to • Pressure and water level control systems maintain the different electrical loading of • Temperature control system for area surrounding individual heaters and simultaneously mimic the the terminals full-scale thermodynamic conditions of the nuclear • Energy supply system power plant for long-duration tests. • Data acquisition system The solution Erecting and operating the test loop meets the Characteristics of KATHAR test facility specifi ed requirements. Depending on the design • Design Data: data of the specimen to be tested, the test loop Pressure: 185 bar can operate up to 7 heaters (nominal power 15 Temperature: 360 °C kW, current up to 700 VAC), each with individual electrical loading. The area surrounding the • Orientation of the test heaters: terminals can be heated to 350 °C or cooled down vertical or horizontal to ambient conditions. A control system monitors • Test specimen: the parameters and manages the electrical up to 7 pcs., single-phase / three-phase cycling. Several threshold limits are set to protect the components from overloading. A makeup • Individual energizing modes and sequences pump and drain valve maintain the water level for each test heater (e.g. 60 ms ON, inside the test vessel. A heat removal system 3.5 s OFF), overlapping / shift ensures the pressure inside the vessel does not • Modern data acquisition and evaluation exceed the set value, independent of the heat produced.

Schematic of the KATHAR test facility Qualification of Components AREVAs Pressurizer Heaters Test Facility / KATHAR

Powerful and self-sustaining test loop • Long-duration, around-the-clock tests lasting several weeks, with varying energization levels and modes, individualized to each specimen • Over 100 temperature sensors on heater surfaces to monitor temperature distributions and avoid damage • Data sampling at different rates for different parameters (e.g. voltage at 1000 Hz, temperature at 1 Hz) • Microcontroller and SIMATIC combine to achieve high stability and accuracy

Electrical cabinet

Intelligent, controlled energy for your components Installed and instrumented specimen

Your benefits at a glance

• Testing under full-scale test conditions • Long duration tests • Integration with and access to AREVA’s thermal-hydraulic platform • Accredited test and inspection body • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-286-V1-14-ENGPB Technical Center - Focus on Technology

Valve Technology and Services ADAM® Diagnostic System to Monitor Operational Availability

The ADAM® Valve Diagnostic System provides important information on the condition and functional behavior of valves and actuators

ADAM® diagnostic system • The diagnostic software performs a detailed ® evaluation for baseline measurements and if The ADAM System periodically inspects the measurement of the active power reveals that operational availability of the complete valve tolerances are being exceeded. If the valve system ranging from the power supply and control exhibits small deviations, it will be surveyed at system to the shutoff device. It compares the the next maintenance cycle. findings with the corresponding baseline measurements in three steps. • Special measurements for root cause analysis are performed directly at the component (e.g., • Online measurement is made of the actuator mechanical parameters such as stem thrust and active power from the switchboard. The torque). These can be incorporated where evaluation proceeds automatically or is menu- necessary. driven using type-specific algorithms. The results are immediately available in a list that shows the To maintain operational parameters within nominal active power converted into mechanical ranges, selective maintenance measures can be parameters such as torque and thrust. The performed as needed. results are compared with nominal ratings and Valve diagnostics reveals changes in the valve and allowable limits. actuator over their lifetimes. This method supports condition-based maintenance. In addition, estimates of the remaining service life of the valves are possible.

ADAM® Valve Diagnostics and Services

Online data acquisition Automatic comparison with Diagnostic software module Special measurements of nominal data mechanical parameters Valve Technology and Services ADAM® Diagnostic System to Monitor Operational Availability

Additional integral valve services ® • The field of valve technology includes sizing ADAM Diagnostic system the valves and actuators as well as evaluating The AREVA GmbH valve monitoring valve design. The functional capability of a system is based on the directly valve design is verified based on qualification proportional relation-ship of the actuator tests under operational conditions, either in active power to the torque exerted during the KOPRA Component Test Facility or on valve operation. The system reliably site. Included in this field are also analysis for monitors all parameters relevant to valve continuous improvement and valve re-fitting. and actuator performance. The software • As an accredited inspection body and with module automatically compares the our test laboratory, we support our measured data against nominal ratings customers with root-cause analysis, reporting and allowable limits. Specified values and diagnostic findings, and discussions with limits are defined using functional and government examiners and regulatory load models that take measurement and authorities. An example is obligatory incident analysis accuracy into account. reporting related to valves. • Solenoid valve services, including functional capability testing with ADAM®. • Services for safety and pilot valves, such as functional testing and in-situ hot adjustments using RESI for spring-loaded pilot valves or RESION for SIERION pressure-activated pilot valves. • Development and qualification of the diagnostic system ADAM® in cooperation with other AREVA departments. Commiss- ioning and on-site courses are also offered. • Maintenance of special valve groups. • Development and manufacture of MDP mobile torque test benches. • Development and manufacture of RESI and RESION test systems.

Your benefits at a glance • Complete scope of products and services for state-of-the-art diagnostics of valves and actuators • Customer support throughout all stages of valve diagnostics, valve design, engineering and maintenance requirements • Accredited test and inspection body, accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-131-V2-13-ENGPB Technical Center - Focus on Technology

Mobile Torque Test Bench - MDP Electrical Actuator Testing

By correlating torque to active power, valve mechanical behavior is determined by measuring active power during operation

The MDP family MDP function Faulty valve operation is often revealed at an early • The MDP consists of an electromagnetic brake. stage by a change in the torque or drive switching The current is proportional to the braking force. behavior. Determining the valve actuator torques After the current is switched off , the residual at regular intervals is therefore useful. With the magnetism inhibits the braking action. In this MDP mobile torque test bench, AREVA GmbH way, the actuator braking torque can be precisely provides a tool for efficiently testing actuators. increased and decreased. MDPs are available in various sizes: • The MDP running torque and moment of inertia are so low that the smallest of standard drives • MDP 50 for actuators with 10 to 60 NM can be tested with precision controlling torque • MDP 200 for actuators with 20 to 200 NM • The digital MDP control unit enables controlling controlling torque. the drives with a variable braking rate. Torque- dependent drives can be slowed down and • MDP 1000 for actuators with 100 to 1000 NM tensioned in the same way as they could be if controlling torque. installed on a valve in-situ. • MDP 3000 for actuators with 300 to 3500 NM controlling torque.

MDP 3000

MDP 1000 MDP 200 MDP 50 MDP family with control and data acquisition Mobile Torque Test Bench - MDP Electrical Actuator Testing

MDP operation MDP as a module of the ADAM® valve • The drive is disconnected from the valve and diagnostic system the MDP is connected to the actuator end Integrating the MDP into the AREVA GmbH shaft with a standard flange. ADAM® Valve Diagnostic System provides the • To determine torque in in-loop operation, the following benefits: electrical wiring remains connected. The • The control device is embedded within actuator is then activated from the plant ADAM®. Interfaces allow ADAM® to control control room or another control facility within the braking rates and record data. the plant. • The measured data are then processed and • To determine the torque during autonomous documented in ADAM® actuator control, the electrical connection is disconnected. The actuator is then activated • Changes in actuation time over the life of the via a separate control unit. actuator can be detected from the active power of the drive motor by comparison with • Using the MDP, the actuator torque is then a measurement recorded at the new increased to the point where the motor is cut conditions. It is not necessary to disassemble out by the torque switch. The measured cut the drive. out torque is immediately compared to the setpoint value. • After testing and adjusting the torque correctly, the actuator is reinstalled on the valve. Upon adjustment of the travel limit switch, the valve is ready for operation again.

ADAM® system with MDP test benches and bench control panel, shown here in a workshop.

Your benefits at a glance • Efficient and precise actuator testing and adjustment • Early diagnosis of faulty valve operation by monitoring at regular intervals  • Integration with ADAM provides ability to evaluate valve mechanical behavior during operation

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-135-V2-13-ENGPB Technical Center - Focus on Technology

RESI - Test System for Pressurizer Safety Valves

RESI ensures the functional reliability of fluid- operated pressurizer safety valves and their pilot trains for PWR plants

RESI functions For safety reasons and to avoid unnecessary stress on system components, the tests are carried out at RESI tests the functional reliability of fluid- a pressure below the closing pressure of the pilot operated pressurizer safety valves and their pilot valves. The RESI test system has been in use at trains both during initial plant startup and during in- many German PWR plants since 1990. This test service inspections each year. On these method meets all requirements of the KTA Nuclear occasions, the spring-loaded pilot valve settings Safety Standards and the Steam Boiler Standard are also checked. TRD 421.

RESI flow chart with auxiliary lift device for spring-loaded pilot valves RESI - Test System for Pressurizer Safety Valves

RESI records valve lift and opening and RESI applications closing pressures. The system automatically and immediately determines test results, such RESI is used on all kinds of spring-loaded as opening and closing reliability, opening and pressurizer safety valves, regardless of their closing delay times and closing differential operation principle, whether based on pressure. The automatic test sequence pressurization or depressurization. The system ensures reproducible test results in all cases. is suitable for a wide range of tests, including: Plug connectors in permanently installed • Pressure-relief valves cabling and subdistributors provide • Setting tests for spring-loaded pilot valves considerable time savings, particularly during performed below their closing pressures test-system setup, test preparations, and (approx. 135 bar). transfer from one valve to the next. These savings in time, along with operating the • Testing pressurizer safety valve actuating controls from a location outside the valve force at partial pilot lift. compartment, reduce the radiation exposure of • Functional testing of the relief train. test personnel. • Functional testing of the primary-system The main features are: bleed function of safety and relief valves, • Less stress on the valves due to extreme including the associated pilot valves. system pressure reduction during the test. • The RESION test system has been developed • In-service adjustment of spring-loaded pilot for testing the settings of SIERION pilot valves valves below their closing pressure without actuated by static pressure primary loop transients. • Remarkable time saving due to ease of test preparation, as well as to automated testing, evaluation and documentation • Easy realization of customer-specific changes in test procedure and documentation. • Self monitoring system reliably prevents unintentional opening of the pilot valves in the event of fault.

Your benefits at a glance • Ensures functional reliability of fluid-operated pressurizer safety valves for PWR plants • Avoids unnecessary stress of system components by testing at lower pressure • Approved test method meets all KTA and steam boiler standard TRD 421 requirements

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-137-V2-13-ENGPB Technical Center - Focus on Technology

System Testing PKL Integral Test Facility

Classroom training course on PWR thermal- hydraulic system behaviour with PKL experimental results

PKL test facility The PKL experimental facility is a scaled-down replication of a 4-loop type PWR. The PKL test facility is scaled to simulate the thermal-hydraulic system behaviour of the full-scale power plant under accident conditions.

Main PKL design features • 4-loop configuration • Heights scaled 1:1 • Volumes scaled 1:145

• up to 10 % of nominal core power

• Max 45 bar of prim. pressure • Max. 60 bar of sec. pressure

Training concept • Training course at NPP site. • Demonstration and analyses of PWR thermal hydraulics on basis of PKL experimental results. • Illustration and analyses of thermal-hydraulic physical phenomena relevant to PWR operation under accident conditions as well as consequences of operator actions Basic thermal-hydraulic principles are conveyed during various accident scenarios. Alternately, the focus can be on a particular scenario and related phenomena, such as primary or secondary feed and-bleed procedures for accident management employed during station blackout or failure of RHRS under cold shutdown conditions. Our skilled trainers have extensive experience in conducting and interpreting integral tests as part of international programs (OECD) and a wide breadth of experience in training NPP personnel. UPTF experiment (1:1 scale) results supply background information on flow phenomena. System Testing PKL Integral Test Facility

Unique and approved training Comprehensive visualization of accident evolution based on PKL results from a broad spectrum of scenarios enhances understanding: • Large break/small break LOCA • Steam generator tube rupture • Main steam line breaks • Station blackout, loss of feedwater transients, efficiency of bleed-and-feed procedures • Systematic studies of thermal-hydraulic phenomena: - Single-/two-phase natural circulation - Reflux-Condenser conditions with/without non-condensable gases

Background: only database of its kind in the world built from more than 160 experiments

Your benefits at a glance • Unique database of PWR thermal hydraulics during operational transients insufficiently covered by TH system codes • Clear explanation of all relevant TH phenomena based on high-resolution database • Accepted by ILAC

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-138-V2-13-ENGPB Technical Center - Focus on Technology

System Testing PWR Integral System Test Facility (PKL)

Live Training Course at the PKL Test Facility

PKL control room panorama

PKL test facility Combination of instruction and test days The PKL experimental facility is a scaled-down Skilled trainers with extensive experience in replication of a 4-loop type PWR. The PKL test conducting and interpreting integral tests as part of facility is scaled to simulate the thermal-hydraulic international programs (OECD), a wide breadth of system behaviour of the full-scale power plant experience in training NPP personnel in ‘live’ training under accident conditions to achieve the following: as well as in classroom training courses at NPP sites are able to discuss: • To analyze overall system responses and system interactions • Details of PWR thermal-hydraulics associated • To demonstrate safety margins and evaluate with the chosen test scenario PWR operating procedures • Test parameters, operator actions and switching operations in PWRs Moreover, parameter studies and tests focusing on separate eff ects contribute to: A database comprising more than 160 • Supply of unique experimental data for thermal experiments on accident scenarios is available hydraulic system code development and validation • Detailed understanding of complex PWR thermal-hydraulic phenomena Main PKL design features

Live training concept • 4-loop configuration • Heights scaled 1:1 Conducting live tests at the PKL test facility on • Volumes scaled 1:145 previously defined scenarios allows demonstration and analysis of PWR thermal-hydraulics as • up to 10 % of nominal core power follows: • max 45 bar of prim. pressure • Demonstrates complex physical phenomena • max. 60 bar of sec. pressure relevant to PWR operation in parallel with progress of accident scenario All safety and operational systems of primary • ‘Live’ training is superior to simulator training and secondary sides courses for demonstrating complex physical phenomena relevant to PWR operation under accident conditions • Demonstrates efficiency of accident management measures System Testing PWR Integral System Test Facility (PKL)

Unique and approved test facility A variety of scenarios can be conducted as live tests: • Small-break LOCA with additional safety system failures, employment of accident management procedures, e.g., primary/ secondary bleed-and feed measures • Main steam line breaks • Station blackout transients with AM- measures to prevent core melt scenario, efficiency of bleed-and feed procedures • Failure of RHRS scenarios under cold shutdown condition Online process visualization • Systematic studies of thermal-hydraulic phenomena involving single-/two-phase natural circulation or reflux-condenser conditions with/without non-condensable gases

Level of authenticity unmatched by conventional simulators

Control panels with switching Observation of individual measuring signals Process elements corresponding to NPP (up to 1500) providing high level of detail visualization tools

PKL control room panorama

Your benefits at a glance • Only 4-loop experimental test facility of its kind in the world models PWR integral system behaviour • PWR thermal hydraulics demonstrated at a level unmatched by conventional simulators • Cutting edge process visualization tools enhance understanding • Compare test results with accident management procedures

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-149-V2-13-ENGPB Technical Center - Focus on Technology

Steam Accumulator Energy Storage for Thermal Processes

Optimize processes with time-varying steam demand

Optimize system operation with energy and economic efficiency Steam supplies energy needs for numerous applications in the fields of power and process technology. The user’s steam demand often varies with time and fluctuates widely so that the steam generator is unable to meet this variable demand. The solution is to use steam accumulators in combination with other thermal accumulators to minimize steam rejection and optimize energy efficiency. During the design phase of new process plants or as a part of refitting existing process plants, we perform a cost-benefit analysis. The Analysis of the process operational behavior analysis consists of five process-oriented steps.

Process-oriented project execution 1. Assess demand Analyze the process plant operational behavior to determine the required steam storage capacity and filling and discharge rates. 2. Design the optimized accumulator Determine the accumulator geometry, accounting for steam demand, time transients and structural boundary conditions.

3. Plan for integration Simulation of transient filling and discharge rates Integrate the steam accumulator into the process plant design. 4. Perform cost-benefit calculation, determine subsidies Compare the required investment and the potential cost savings. When appropriate, determine subsidies. 5. Project execution One business partner accompanies the owner from the design to the commissioning phase.

Integration concept for the steam accumulator Steam Accumulator Energy Storage for Thermal Processes

AREVA owner-operated steam accumulators

Our many years of experience in the • Designing control technology for power and aspects below contribute to successful process plants project management: • Simulating transient filling and discharge rates of steam accumulators using • Operating many types of steam accumulators configuration programs with varied filling and discharge rates • Designing and constructing power and process • Commissioning power plants and process plants plants • Executing projects involving entire plants

Your benefits at a glance • Analysis and optimization of steam storage • Analysis and optimization of steam accumulator geometry • Customized design for individual processes • Cost-benefit calculation • Project execution with a single partner • Operational experience with our own steam accumulators

AREVA GMBH Your contact: [email protected] Back to content

„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-174-V1-14-ENGPB Technical Center - Focus on Technology

Unit Conversion Table

Conversion between international system of units (SI units) and British or US system of units

Physical British or US system of units to SI units SI units to British or US system of units quantity

Acceleration 1 ft/s² = 0.30480 m/s² 1 m/s² = 3.28083985 ft/s²

Area 1 sq in = 0.64516·10-3 m² 1 m² = 1.550003·103 sq in 1 sq ft = 0.09290304 m² 1 m² = 10.76391 sq ft 1 sq yd = 0.83612736 m² 1 m² = 1.195990 sq yd 1sq mi = 2.589988·106 m² 1 m² = 0.3861022·10-6 sq mi

Density 1 lb/ft³ = 16.01846 kg/m³ 1 kg/m³ = 0.06242797 lb/ft³

Dynamic 1 lbf s/sqft = 47.88026 Ns/m² 1 Ns/m² = 20.88543·10-3 lbf s/sqft viscosity

Energy 1 hp hr = 2.684520·106 J 1 J = 372.5061·10-9 hp hr 1 PSh = 2.6477955·106 J 1 J = 377.6727·10-9 PSh 1 BTU = 1055.056 J 1 J = 947.8171·10-6 BTU 1 lbf-ft = 1.355818 J 1 J = 737.5621·10-3 lbf-ft

Force 1 pdl = 138.2550·10-3 N 1 N = 7.233014 pdl 1 lbf = 1 lb wt = 4.448222 N 1 N = 224.8089·10-3 lbf; lb wt 1 sh tn = 8896.443 N 1 N = 112.4045·10-6 sh tn 1 l tn = 9964.016 N 1 N = 100.3611·10-6 l tn

Heat 1 BTU/(in h R) = 20.76882 W/(mK) 1 W/(mK) = 48.14911·10-3 BTU/(in h R) conductivity 1 BTU/(ft h R) = 1.730735 W/(mK) 1 W/(mK) = 577.7893·10-3 BTU/(ft h R) 1 BTU/(yd h R) = 576.9116·10-3 W/(mK) 1 W/(mK) = 1.73368 BTU/(yd h R)

Heat transfer 1 BTU/(sq in h R) = 817.6699 W/(m² K) 1 W/(m² K) = 1.222987·10-3 BTU/(sq in h R) coefficient 1 BTU/(sq ft h R) = 5.6782633 W/(m² K) 1 W/(m² K) = 176.1102·10-3 BTU/(sq ft h R) 1 BTU/(sq yd h R) = 630.9181·10-3 W/(m² K) 1 W/(m² K) = 1.584992 BTU/(sq yd h R)

Length 1 in = 25.4·10-3 m 1 m = 39.37008 in 1 ft = 0.3048 m 1 m = 3.280840 ft 1 yd = 0.9144 m 1 m = 1.093613 yd 1 mi = 1609.344 m 1 m = 0.6213712·10-3 mi

Mass (inertia) 1 lb = 0.45359247 kg 1 kg = 2.204623 lb 1 stone = 6.3502932 kg 1 kg = 157.47304·10-3 stone 1 quarter = 12.700586 kg 1 kg = 78.73652·10-3 quarter 1 long ton (Brit.) = 1,016.0469 kg 1 kg = 984.2065·10-6 long tons (Brit.) 1 short ton (USA) = 907.18474 kg 1 kg = 1.102311·10-3 short tons (USA)

Mass flow 1 lb/min = 27.2155422 kg/h 1 kg/h = 0.036743710 lb/min 1 lb/min = 7.55987283·10-3 kg/s 1 kg/s = 132.277357 lb/min 1 lb/min = 0.0272155422 t/h 1 t/h = 36.743710 lb/min

Unit Conversion Table

Physical British or US system of units SI units to British or US system quantity to SI units of units

Power 1 BTU/s = 1055.056 W 1 W = 947.8171·10-6 BTU/s 1 hp = 745.6999 W 1 W = 1.341022·10-3 hp 1 PS = 1 cv = 735.49875 W 1 W = 1.359622·10-3 PS; cv 1 ft Lb/s = 1.355818 W 1 W = 0.7375621 ft Lb/s

Pressure 1 psi = 6894.757 N/m² (Pa) 1 N/m² (Pa) = 145.04·10-6 psi 1 psi = 0.06895 bar 1 bar = 14.504 psi 1 psf = 47.88026 N/m² (Pa) 1 N/m² (Pa) = 20.88543·10-3 psf -3 1 in H2O = 249.08891 N/m² (Pa) 1 N/m² (Pa) = 4.014631·10 in H2O 1 in Hg = 3386.379 N/m² (Pa) 1 N/m² (Pa) = 295.3007·10-6 in Hg -6 1 ft H2O = 2989.067 N/m² (Pa) 1 N/m² (Pa) = 334.5526·10 ft H2O 1 ft Hg = 40636.55 N/m² (Pa) 1 N/m² (Pa) = 24.60839·10-6 ft Hg

Specific 1 BTU/lb = 2326 J/kg 1 J/kg = 429.9226·10-6 BTU/lb enthalpy

Specific heat 1 BTU/(lb R) = 4186.8 J/(kg K) 1 J/(kg K) = 238.8459·10-6 BTU/(lb R) capacity

Temperature T(°F) = 9/5 · T(°C) + 32 T(°C) = 5/9 · (T(°F) – 32) 0 K = - 273.15°C 0°C = 273.15 K

Torque 1 in lbf = 0.11300 Nm 1 Nm = 8.8496 in lbf 1 ft lbf = 1.35582 Nm 1 Nm = 0.73756 ft lbf

Velocity 1 ft/min = 0.00508 m/s 1 m/s = 196.85039 ft/min 1 mph = 1.609344 km/h 1 km/h = 0.62137119 mph

Volume 1 cu in = 16.38706·10-6 m³ 1 m³ = 61.02374·103 cu in 1 cu ft = 0.02831685 m³ 1 m³ = 35,31467 cu ft 1 cu yd = 0.7645549 m³ 1 m³ = 1.307951 cu yd 1 gal (Brit.) = 4.54609·10-3 m³ 1 m³ = 219.96925 gal (Brit.) 1 gal (USA) = 3.785411784·10-3 m³ 1 m³ = 264.17205 gal (USA)

Volume flow 1 gal/min (USA) = 0.22712 m³/h 1 m³/h = 4.40288 gal/min (USA) 1gal/min (Brit.) = 0.272766 m³/h 1 m³/h = 3.6661 gal/min Brit.) 1ft³/s = 101.940648 m³/h 1 m³/h = 9.809629·10-3 ft³/s 1ft³/s = 0.02831685 m³/s 1 m³/s = 35.3146667 ft³/s Unit conversion table

Physical Equivalent units in the metric system Power of Prefix Symbol quantity ten

Force 1 N = 1 J/m = 1 m kg/s² 106 mega M

Mass 1 t = 10³ kg = 1 Mg; 1 g = 10-3 kg 103 kilo k

Mass flow 1 t/h = 3.6-1 kg/s; 1 kg/h = 3600-1 kg/s 102 Hecto h

Pressure 1 Pa = 1 N/m² = 1 kg/(m s²); 1 bar = 105 Pa 10-1 deci d

Velocity 1 km/h = 3.6-1 m/s 10-3 milli m

Volume 1 l = 1 dm³ = 10-3 m³ 10-6 micro µ

Volume flow 1 m³/h = 3600-1 m³/s; 1 l/min = 60,000-1 m³/s 10-9 nano n

Conversion factors Prefixes and Symbols

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„Editor and Copyright (2015): AREVA GmbH – Paul-Gossen-Straße 100 – 91052 Erlangen, Germany. It is prohibited to reproduce the present publication in its entirety or partially in whatever form without prior written consent. Legal action may be taken against any infringer and/or any person breaching the aforementioned prohibitions. Subject to change without notice, errors excepted. Illustrations may differ from the original. The statements and information contained in this publication are for advertising purposes only and do not constitute an offer of contract. They shall neither be construed as a guarantee of quality or durability, nor as warranties of merchantability or fitness for a particular purpose. These statements, even if they are future-orientated, are based on information that was available to us at the date of publication. Only the terms of individual contracts shall be authoritative for type, scope and characteristics of our products and services.” G-187-V1-14-ENGPB cts cts shall be authoritative for type,

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Contact: AREVA GmbH ⋅ Technical Center ⋅ Paul-Gossen-Strasse 100 ⋅ 91052 Erlangen ⋅ Germany scope and characteristics of our products and services. our products of and characteristicsscope breaching the aforementioned as construed a guarantee of qualityornor durability, as of warranties and for a particularmerchantability purpose. fitness Phone: +49 (0)9131 900 95140 ⋅ Fax: +49 (0)9131 900 94024 Editor and Copyright [2016]: