STERN LABORATORIES INC. CUSTOMERS

(Click on Countries)

Click here or the logo to go to our website

about us.

Stern Laboratories Inc. is a Canadian owned private corporation that conducts reliability and safety experiments for utilities, nuclear reactor and fuel vendors, government agencies and nuclear equipment suppliers. The laboratory has modern computer data acquisition systems, a 16 MW DC power supply with 13 individually controlled zones, and is one of the highest power and most versatile heat transfer facilities in the world.

We also manufacture specialized equipment, such as electrically heated nuclear fuel simulators and devices for inspection and handling of spent nuclear fuel. We have a highly skilled and experienced staff of professional engineers and engineering technologists and have served the Nuclear Industry in Canada and in many other countries since 1962.

The laboratory specializes in the design and construction of complex experimental facilities and devices to simulate CANDU, BWR (Boiling Water Reactors) and PWR (Pressurized Water Reactors) heat transport systems, safety systems, reactor fuel and fuel channel components, conducting the experiments and analyzing and reporting the results. Highly specialized computing hardware and software are available for precise control of the experimental conditions and fo r high speed, accurate acquisition and reduction of the data. The laboratory facilities are continually being upgraded to meet the diverse needs of customers. Space and services are readily available for new experiments.

Critical Heat Flux (CHF) Experiments.

Critical Heat Flux (CHF) tests have been successfully performed in full scale, horizontal CANDU fuel channels at reactor operating conditions using directly heated fuel simulations representing 28-element, 37-element and 43-element CANDU fuel. The fuel simulations are equipped with movable internal thermocouples which can be remotely positioned to monitor critical power (dryout) over most of the surfaces of the downstream bundle elements. 

Boiling Transition (BT) tests have been successfully performed in full-scale vertical BWR fuel channels (up to 10×10 bundle arrays) at reactor operating conditions using indirectly heated fuel simulators equipped with internal thermocouples (up to 12 per rod) at precise locations to determine critical power. 

Departure from Nucleate Boiling (DNB) tests have been successfully performed in vertical PWR channels (up to 5×5 bundle arrays) at reactor operating conditions using indirectly heated fuel simulators equipped with internal thermocouples (up to 12 per rod) at precise locations to determine critical power. 

The power supply has up to 16 megawatts of 12 pulse rectified DC power available with 13 controlled power zones which operate individually at up to 330 volts to neutral or in pairs at up to 660 volts differential (+330 to -330 volts). 

Remote Handling Tools, Fuel Handling & Inspection Services.

A variety of tools have been designed, fabricated and tested for use in remote inspection and handling of spent (used) nuclear fuel which is stored underwater in pools at nuclear stations.

Tools suitable for grasping, prying and surface cleaning operations which are performed at the bottom of the fuel inspection pools have been adapted for use with a universal tool handle which is manually actuated from above the pool.  Tools are fabricated from passivated stainless steel to minimize corrosion.

A “Light Pipe” camera system has been developed to provide fuel inspectors with high resolution video for performing underwater inspections and other operations as a replacement for expensive periscopes.

A “Chopper Tool” system has been developed for removing irradiated In-Core (neutron) Flux Detectors (ICFD) from a CANDU reactor.  

A large water tank which simulates the spent fuel bay in a nuclear reactor is used for testing prototypes of the inspection tools and for training fuel inspectors.

Fuel Simulators.

Stern Laboratories manufactures highly reliable electrically heated nuclear fuel simulators which are designed and built to meet the particular requirements of each customer application. 

We build indirectly heated fuel simulators which have the same external geometry and heat generation as real fuel and are used to perform heat transfer experiments in our laboratory and other laboratories around the world. 

We fabricate many types of indirectly heated fuel simulators for BWR (Boiling Water Reactors), PWR (Pressurized Water Reactors) and CANDU applications. There are several sample heaters with cross-section views to show construction details, such as the filament (electrical heating element), the Boron Nitride electrical insulation used between the filament and the Inconel or Monel stainless steel sheath and outer cladding, and the installation of internal thermocouples. Specialty fuel simulators, containing hollow pellets (UO₂ or other material) with the electric heater passing through the pellets, capable of very steep temperature ramps to over 1100°C are also designed and built. 

Reactor Safety and Reliability Experiments.

Numerous large and small-scale facilities have been fabricated to simulate various nuclear reactor components and experiments.

These experiments have been performed simulating normal operation, as well as accident scenarios (often involving high energy levels) to provide data for code validation and licensing submissions. 

Stern Laboratories has a design team and construction crew that can rapidly bring new experimental development facilities into service and adapt requested changes to meet new customer requirements.

Computational Fluid Dynamics (CFD).

Advanced analytical techniques are used to simulate in-reactor conditions and obtain knowledge in lieu of costly experiments. The work performed at Stern includes analyses of the cross-sectional temperature distribution inside a CANDU crept channel, turbulence modelling of flow disturbance due to bundle appendages and bundle misalignment effects using advanced software packages.

Advanced CFD methods and turbulence models are used with single and multiphase schemes. The wall boiling and partitioning methods are well-suited for modelling heat transfer trends and its dependence on sub cooling along a fuel channel. The meshing module of the software uses the most recent techniques to provide quality meshes for complex geometries.

Flux Detector Removal Tool (Chopper Tool).

CANDU reactors employ many In-Core neutron Flux Detectors (ICFD) that are installed in the reactor core to monitor the neutron flux level for normal reactor operating conditions. An ICFD is made from an Inconel wire, 1 to 3 mm diameter over 20 metres long, and coated with Vanadium or Platinum. The life time of the ICFD is about 10 to 20 years, after which it must be removed and replaced.

Stern Laboratories manufactures and supplies remotely operated tools to CANDU nuclear power stations in Canada and other countries to remove the highly radioactive IFCDs.

The spent ICFD is removed by chopping the detector wire into short lengths as it is pulled from the reactor, and transporting the short lengths into shielded temporary storage containers using a vacuum system. Up to 12 IFCD containers can be stored in a lead shielded flask that can then be easily transferred to permanent storage.

Single Element High Pressure Loop.

This compact pressurized water loop is used to perform DNB (or CHF) tests using a short length, indirectly heated, single element fuel simulator. The test rig was constructed to perform a series of experiments to investigate the effects of dissolved nitrogen gas in the coolant on CHF performance at PWR conditions. The loop is designed to operate at pressures up to 20.8 MPa and temperatures up to 371° C. The circulating pump is capable of supplying cooling water up to 1.89 litres/second. The sampling system shown below on the right is used to verify the dissolved nitrogen gas content in the loop coolant.

Single Phase Pressure Drop Loop.

This compact loop is an ideal facility for performing experiments to measure the pressure drop performance of new BWR fuel channel components. We have tested many prototype fuel supports, strainers and other BWR components. 

This loop can also be used for performing high temperature and pressure endurance experiments.

Click here or the logo to go to our website

STER N LABORATORIES INC. CUSTOMERS

(Click on Countries)

about us.

Stern Laboratories Inc. is a Canadian owned private corporation that conducts reliability and safety experiments for utilities, nuclear reactor and fuel vendors, government agencies and nuclear equipment suppliers. The laboratory has modern computer data acquisition systems, a 16 MW DC power supply with 13 individually controlled zones, and is one of the highest power and most versatile heat transfer facilities in the world.

We also manufacture specialized equipment, such as electrically heated nuclear fuel simulators and devices for inspection and handling of spent nuclear fuel. We have a highly skilled and experienced staff of professional engineers and engineering technologists and have served the Nuclear Industry in Canada and in many other countries since 1962.

The laboratory specializes in the design and construction of complex experimental facilities and devices to simulate CANDU, BWR (Boiling Water Reactors) and PWR (Pressurized Water Reactors) heat transport systems, safety systems, reactor fuel and fuel channel components, conducting the experiments and analyzing and reporting the results. Highly specialized computing hardware and software are available for precise control of the experimental conditions and fo r high speed, accurate acquisition and reduction of the data. The laboratory facilities are continually being upgraded to meet the diverse needs of customers. Space and services are readily available for new experiments.

Critical Heat Flux (CHF) Experiments.

Critical Heat Flux (CHF) tests have been successfully performed in full scale, horizontal CANDU fuel channels at reactor operating conditions using directly heated fuel simulations representing 28-element, 37-element and 43-element CANDU fuel. The fuel simulations are equipped with movable internal thermocouples which can be remotely positioned to monitor critical power (dryout) over most of the surfaces of the downstream bundle elements. 

Boiling Transition (BT) tests have been successfully performed in full-scale vertical BWR fuel channels (up to 10×10 bundle arrays) at reactor operating conditions using indirectly heated fuel simulators equipped with internal thermocouples (up to 12 per rod) at precise locations to determine critical power. 

Departure from Nucleate Boiling (DNB) tests have been successfully performed in vertical PWR channels (up to 5×5 bundle arrays) at reactor operating conditions using indirectly heated fuel simulators equipped with internal thermocouples (up to 12 per rod) at precise locations to determine critical power. 

The power supply has up to 16 megawatts of 12 pulse rectified DC power available with 13 controlled power zones which operate individually at up to 330 volts to neutral or in pairs at up to 660 volts differential (+330 to -330 volts). 

Remote Handling Tools, Fuel Handling & Inspection Services.

A variety of tools have been designed, fabricated and tested for use in remote inspection and handling of spent (used) nuclear fuel which is stored underwater in pools at nuclear stations.

Tools suitable for grasping, prying and surface cleaning operations which are performed at the bottom of the fuel inspection pools have been adapted for use with a universal tool handle which is manually actuated from above the pool.  Tools are fabricated from passivated stainless steel to minimize corrosion.

A “Light Pipe” camera system has been developed to provide fuel inspectors with high resolution video for performing underwater inspections and other operations as a replacement for expensive periscopes.

A “Chopper Tool” system has been developed for removing irradiated In-Core (neutron) Flux Detectors (ICFD) from a CANDU reactor.  

A large water tank which simulates the spent fuel bay in a nuclear reactor is used for testing prototypes of the inspection tools and for training fuel inspectors.

Fuel Simulators.

Stern Laboratories manufactures highly reliable electrically heated nuclear fuel simulators which are designed and built to meet the particular requirements of each customer application. 

We build indirectly heated fuel simulators which have the same external geometry and heat generation as real fuel and are used to perform heat transfer experiments in our laboratory and other laboratories around the world. 

We fabricate many types of indirectly heated fuel simulators for BWR (Boiling Water Reactors), PWR (Pressurized Water Reactors) and CANDU applications. There are several sample heaters with cross-section views to show construction details, such as the filament (electrical heating element), the Boron Nitride electrical insulation used between the filament and the Inconel or Monel stainless steel sheath and outer cladding, and the installation of internal thermocouples. Specialty fuel simulators, containing hollow pellets (UO₂ or other material) with the electric heater passing through the pellets, capable of very steep temperature ramps to over 1100°C are also designed and built. 

Reactor Safety and Reliability Experiments.

Numerous large and small-scale facilities have been fabricated to simulate various nuclear reactor components and experiments.

These experiments have been performed simulating normal operation, as well as accident scenarios (often involving high energy levels) to provide data for code validation and licensing submissions. 

Stern Laboratories has a design team and construction crew that can rapidly bring new experimental development facilities into service and adapt requested changes to meet new customer requirements.

Computational Fluid Dynamics (CFD).

Advanced analytical techniques are used to simulate in-reactor conditions and obtain knowledge in lieu of costly experiments. The work performed at Stern includes analyses of the cross-sectional temperature distribution inside a CANDU crept channel, turbulence modelling of flow disturbance due to bundle appendages and bundle misalignment effects using advanced software packages.

Advanced CFD methods and turbulence models are used with single and multiphase schemes. The wall boiling and partitioning methods are well-suited for modelling heat transfer trends and its dependence on sub cooling along a fuel channel. The meshing module of the software uses the most recent techniques to provide quality meshes for complex geometries.

Flux Detector Removal Tool (Chopper Tool).

CANDU reactors employ many In-Core neutron Flux Detectors (ICFD) that are installed in the reactor core to monitor the neutron flux level for normal reactor operating conditions. An ICFD is made from an Inconel wire, 1 to 3 mm diameter over 20 metres long, and coated with Vanadium or Platinum. The life time of the ICFD is about 10 to 20 years, after which it must be removed and replaced.

Stern Laboratories manufactures and supplies remotely operated tools to CANDU nuclear power stations in Canada and other countries to remove the highly radioactive IFCDs.

The spent ICFD is removed by chopping the detector wire into short lengths as it is pulled from the reactor, and transporting the short lengths into shielded temporary storage containers using a vacuum system. Up to 12 IFCD containers can be stored in a lead shielded flask that can then be easily transferred to permanent storage.

Single Element High Pressure Loop.

This compact pressurized water loop is used to perform DNB (or CHF) tests using a short length, indirectly heated, single element fuel simulator. The test rig was constructed to perform a series of experiments to investigate the effects of dissolved nitrogen gas in the coolant on CHF performance at PWR conditions. The loop is designed to operate at pressures up to 20.8 MPa and temperatures up to 371° C. The circulating pump is capable of supplying cooling water up to 1.89 litres/second. The sampling system shown below on the right is used to verify the dissolved nitrogen gas content in the loop coolant.

Single Phase Pressure Drop Loop.

This compact loop is an ideal facility for performing experiments to measure the pressure drop performance of new BWR fuel channel components. We have tested many prototype fuel supports, strainers and other BWR components. 

This loop can also be used for performing high temperature and pressure endurance experiments.

STER N LABORATORIES INC. CUSTOMERS

aecl  |  alied signal  |  amag  |  amec  |  AMEC FOSTER WHEELER  |  BABCOCK & WILCOX  |  bruce power  |  BWXT CANADA LIMITEd  |  cameco  |  canaton  |  CANDU OWNERS GROUP  |  CANTECH ASSOCIATES, LTD.  |  cbs  |  CCI THERMAL TECHN.  |  cnsc  |  cnno  |  dresser  |  endress & hauser  |  es fox  |  eti  |  fike  |  foxboro  |  GE HITACHI  |  gnest  |  HAMILTON PORT AUT HORITY  |  hope innovations  |  HYDRO QUEBEC  |  INGERSOLL-RAND  |  kinectrics  |  labbat's  |  LAKEPORT BREWING  |  LAKER ENERGY PRODUCTS  |  McMASTER UNIVERSITY  |  NEW BRUNSWICK POWER  |  nigara energy  |  nss  |  opg  |  russel metals  |  siemens  |  sihi pumps  |  taylor forge  |  UNIVERSITY OF MANITOBA  |  zircatec

alstom power  |  BABCOCK & WILCOX m POWER  |  columbia university  |  creare  |  GE GLOBAL RESEARCH  |  general electric  |  gnf  |  hexatron  |  holtec  |  honeywell  |  kansas state university  |  nuscale power  |  valcor  |  UNIVERSITY OF WISCONSIN  |  UNIVERSITY OF SOUTH CAROLINA  |  terra power  |  TEXAS A & M UNIVERSITY

NUCLEOELECTRICA ARGENTINA

(NASA)

abb atom  |  studsvik  |  westinghouse

cegb

areva

SOCIETATA NATIO NALA NUCLEARELCTRICA (SNN)

nri

cea  |  edf  |  irsn

enusa

GE HITACHi  |  iae  |  gnf  |  nfi  |  MHI  |  toshiba

CIAE  |  cnno  |  SNPTR&D  

kaeri  |  kepri

abo ut us.

Stern Laboratories Inc. is a Canadian owned private corporation that conducts reliability and safety experiments for utilities, nuclear reactor and fuel vendors, government agencies and nuclear equipment suppliers. The laboratory has modern computer data acquisition systems, a 16 MW DC power supply with 13 individually controlled zones, and is one of the highest power and most versatile heat transfer facilities in the world.

We also manufacture specialized equipment, such as electrically heated nuclear fuel simulators and devices for inspection and handling of spent nuclear fuel. We have a highly skilled and experienced staff of professional engineers and engineering technologists and have served the Nuclear Industry in Canada and in many other countries since 1962.

The laboratory specializes in the design and construction of complex experimental facilities and devices to simulate CANDU, BWR (Boiling Water Reactors) and PWR (Pressurized Water Reactors) heat transport systems, safety systems, reactor fuel and fuel channel components, conducting the experiments and analyzing and reporting the results. Highly specialized computing hardware and software are available for precise control of the experimental conditions and fo r high speed, accurate acquisition and reduction of the data. The laboratory facilities are continually being upgraded to meet the diverse needs of customers. Space and services are readily available for new experiments.

Critical Heat Flux (CHF) Experiments.

Critical Heat Flux (CHF) tests have been successfully performed in full scale, horizontal CANDU fuel channels at reactor operating conditions using directly heated fuel simulations representing 28-element, 37-element and 43-element CANDU fuel. The fuel simulations are equipped with movable internal thermocouples which can be remotely positioned to monitor critical power (dryout) over most of the surfaces of the downstream bundle elements. 

Boiling Transition (BT) tests have been successfully performed in full-scale vertical BWR fuel channels (up to 10×10 bundle arrays) at reactor operating conditions using indirectly heated fuel simulators equipped with internal thermocouples (up to 12 per rod) at precise locations to determine critical power. 

Departure from Nucleate Boiling (DNB) tests have been successfully performed in vertical PWR channels (up to 5×5 bundle arrays) at reactor operating conditions using indirectly heated fuel simulators equipped with internal thermocouples (up to 12 per rod) at precise locations to determine critical power. 

The power supply has up to 16 megawatts of 12 pulse rectified DC power available with 13 controlled power zones which operate individually at up to 330 volts to neutral or in pairs at up to 660 volts differential (+330 to -330 volts). 

Remote Handling Tools, Fuel Handling & Inspection Services.

A variety of tools have been designed, fabricated and tested for use in remote inspection and handling of spent (used) nuclear fuel which is stored underwater in pools at nuclear stations.

Tools suitable for grasping, prying and surface cleaning operations which are performed at the bottom of the fuel inspection pools have been adapted for use with a universal tool handle which is manually actuated from above the pool.  Tools are fabricated from passivated stainless steel to minimize corrosion.

A “Light Pipe” camera system has been developed to provide fuel inspectors with high resolution video for performing underwater inspections and other operations as a replacement for expensive periscopes.

A “Chopper Tool” system has been developed for removing irradiated In-Core (neutron) Flux Detectors (ICFD) from a CANDU reactor.  

A large water tank which simulates the spent fuel bay in a nuclear reactor is used for testing prototypes of the inspection tools and for training fuel inspectors.

Fuel Simulators.

Stern Laboratories manufactures highly reliable electrically heated nuclear fuel simulators which are designed and built to meet the particular requirements of each customer application. 

We build indirectly heated fuel simulators which have the same external geometry and heat generation as real fuel and are used to perform heat transfer experiments in our laboratory and other laboratories around the world. 

We fabricate many types of indirectly heated fuel simulators for BWR (Boiling Water Reactors), PWR (Pressurized Water Reactors) and CANDU applications. There are several sample heaters with cross-section views to show construction details, such as the filament (electrical heating element), the Boron Nitride electrical insulation used between the filament and the Inconel or Monel stainless steel sheath and outer cladding, and the installation of internal thermocouples. Specialty fuel simulators, containing hollow pellets (UO₂ or other material) with the electric heater passing through the pellets, capable of very steep temperature ramps to over 1100°C are also designed and built. 

Reactor Safety and Reliability Experiments.

Numerous large and small-scale facilities have been fabricated to simulate various nuclear reactor components and experiments.

These experiments have been performed simulating normal operation, as well as accident scenarios (often involving high energy levels) to provide data for code validation and licensing submissions. 

Stern Laboratories has a design team and construction crew that can rapidly bring new experimental development facilities into service and adapt requested changes to meet new customer requirements.

Computational Fluid Dynamics (CFD).

Advanced analytical techniques are used to simulate in-reactor conditions and obtain knowledge in lieu of costly experiments. The work performed at Stern includes analyses of the cross-sectional temperature distribution inside a CANDU crept channel, turbulence modelling of flow disturbance due to bundle appendages and bundle misalignment effects using advanced software packages.

Advanced CFD methods and turbulence models are used with single and multiphase schemes. The wall boiling and partitioning methods are well-suited for modelling heat transfer trends and its dependence on sub cooling along a fuel channel. The meshing module of the software uses the most recent techniques to provide quality meshes for complex geometries.

Flux Detector Removal Tool (Chopper Tool).

CANDU reactors employ many In-Core neutron Flux Detectors (ICFD) that are installed in the reactor core to monitor the neutron flux level for normal reactor operating conditions. An ICFD is made from an Inconel wire, 1 to 3 mm diameter over 20 metres long, and coated with Vanadium or Platinum. The life time of the ICFD is about 10 to 20 years, after which it must be removed and replaced.

Stern Laboratories manufactures and supplies remotely operated tools to CANDU nuclear power stations in Canada and other countries to remove the highly radioactive IFCDs.

The spent ICFD is removed by chopping the detector wire into short lengths as it is pulled from the reactor, and transporting the short lengths into shielded temporary storage containers using a vacuum system. Up to 12 IFCD containers can be stored in a lead shielded flask that can then be easily transferred to permanent storage.

Single Element High Pressure Loop.

This compact pressurized water loop is used to perform DNB (or CHF) tests using a short length, indirectly heated, single element fuel simulator. The test rig was constructed to perform a series of experiments to investigate the effects of dissolved nitrogen gas in the coolant on CHF performance at PWR conditions. The loop is designed to operate at pressures up to 20.8 MPa and temperatures up to 371° C. The circulating pump is capable of supplying cooling water up to 1.89 litres/second. The sampling system shown below on the right is used to verify the dissolved nitrogen gas content in the loop coolant.

Single Phase Pressure Drop Loop.

This compact loop is an ideal facility for performing experiments to measure the pressure drop performance of new BWR fuel channel components. We have tested many prototype fuel supports, strainers and other BWR components. 

This loop can also be used for performing high temperature and pressure endurance experiments.