Overview of Advanced
Reactor Research Capabilities

Janelle Eddins
Advanced Reactor Development
Team Lead
Janelle.eddins@nuclear.energy.gov

Mechanisms
Engineering Test Loop(METL)•To test small or intermediate scale advanced liquid metal components andinstrumentation in sodium and to train the next generation of engineers on sodium
experiments•

METL consists of:•~3,000 kg of reactor-grade sodium – purified in cold trap•

Two 18-inch and two 28-inch test vessels, four more vessels planned•

Max system temperature = 537.8°C (1000°F) (except for 28-inch test vessels –648.9°C (1200°F))•Test vessels can be isolated from main loop•

The facility started operations in September 2018•

Test Articles:•Gear Test Assembly (GTA) and Gripper Test Article (GrTA)•Thermal Hydraulic Experimental Test Article (THETA)•Flow Sensor Test Article (F-STAr)• See: https://www.anl.gov/nse/mechanisms-engineering-test-loop-facility

Contact: Bo Feng (ANL), bofeng@anl.gov; Chris Grandy (ANL), cgrandy@anl.gov

Liquid Salt TestLoop (LSTL)
Largest F salt loop in DOESalt

NaF-KF-LiF (FLiNaK)Operating Temp.

700oC

Flow rate≤4.5 kg/s (136 lpm)

Operating pressure

Near atmosphericPrimary Materials

Inconel 600

Loop volume80 liters

Power200 kW induction~20 kW trace

Primary piping ID

2.67 cm (1.05 in.)Initial operation

Summer 2016

Contact: Kevin Robb (ORNL), robbkr@ornl.gov

Current Test Focus:• Chemistry monitoring and control• Species transport and off-gas
monitoring• Novel instrumentation testing• Test data for SAM, MELCOR,
and other tools
Example NEUP Collaborations:• Coupon exposure• New sensor testing anddemonstration• Modeling & Sim. comparisons• Component characterization

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Facility to Alleviate
Salt Technology
Risks (FASTR)
Largest Cl salt loop in DOE
SaltNaCl-KCl-MgCl2

Operating Temp.

725oC

Flow rate≤7.0 kg/s (228 lpm)

Operating pressure

Near atmosphericPrimary Materials

C-276 & Inconel 600

Loop volume

154 liters

Power400 kW Main Heater~71 kW trace

Primary piping ID

5.20 cm (2.05 in.)Initial operation

December 2022

Contact: Kevin Robb (ORNL), robbkr@ornl.gov

Current Test Goals:• Chemistry and corrosion control• System thermal hydraulics• Digit twin demonstration• Extended/life testing
Example NEUP Collaborations:• Coupon exposure• New sensor testing anddemonstration• Modeling & Sim. Comparisons• Salt purification approaches

Robb, Kevin, and Kappes, Ethan. Facility toAlleviate Salt Technology Risks (FASTR):
Commissioning Update. United States: ORNL/TM2023/2846, 2023. Web. doi:10.2172/1960689.
Robb, Kevin, Kappes, Ethan, and Mulligan,Padhraic L. Facility to Alleviate Salt
Technology Risks (FASTR): Design Report. UnitedStates: ORNL/TM-2022/2803, 2022. Web.
doi:10.2172/1906574.

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Heat Pipes and Filling
Capability• Heat pipes are a heat transfer mechanism for microreactorsthat can remove heat from one part (the bottom) of the core
to another quickly using a working material such as sodium.
• The eFill37 is a scalable heat pipe charging and sealing
apparatus developed with the intent of easing andautomating the manufacture of heat-pipe-cooled
microreactors.
eFill37 andmetered fillprocess

Plug Loader
Contact: Holly Trellue (LANL), Trellue@lanl.gov

Single Primary Heat Extraction and Removal Emulator(SPHERE) SPHERE_Factsheet_MRP_May2022.pdf(inl.gov)
Provide capabilities to perform steady-state and transient
testing of heat pipes and heat transfer:• Wide range of heating values and operating temperatures• Observe heat pipe startup and transient operation
Develop effective thermal coupling methods between theheat pipe outer surface and core structures
Measure heat pipe axial temperature profiles during startup,
steady-state, and transient operation using thermal imaging
and surface measurements

Contact: Piyush Sabharwall (INL), piyush.sabharwall@inl.gov

Parameter

Value

Length10 ft

Diameter

12 inTube material

Stainless steel

Connections

Flanged for gas flow
and instrumentationfeedthroughMaximum power

20 kW

Max temperature

900 C

Heat removal

Passive radiation orwater-cooled gas gap
calorimeter

Microreactor AGile Non-nuclear Experimental Testbed(MAGNET)•General purpose test bed for performance evaluation of
microreactor design concepts (heat pipe, gas-cooled, other)

Parameter

Value

Chamber size

5 ft x 5 ft x 10 ft

Provide detailed reactor core and heat removal section
thermal hydraulic performance data for prototypicalgeometries and operating conditions

Heat removal

Liquid-cooled chamber walls

Connections

Demonstrate interface of heat removal section and coresectionFlanged for gas flow,instrumentation feedthroughs,
and viewing windows

Coolants

Air, inert gas (He, N2)•Provides for integrated materials and instrumentation testingGas flow rates

Up to 43.7 ACFM at 290 psig•

Co-located with integrated energy systems R&D capabilities

Design pressure

22 barg

Maximum power

250 kW

Max test article
temperature

750°C

Heat removal

Passive radiation or forcedgas cooling••Contact: Piyush Sabharwall (INL), piyush.sabharwall@inl.gov

Helium Component Test Facility• Helium Component Test Facility (He-CTF) integrates with MAGNET
infrastructure to provide additional testing capability for reactor
developers•

Provides access to a facility used to validate component performance in a flowing or
stagnant high-temperature, high-pressure, helium environment•

Will reduce time and cost associated with demonstration of non-irradiated reactor
components in a near-prototypic environment•

Helium Operating Parameters: pressure up to 20 bar, flow up to 70 g/s, and temp up to 650°C•

INL collects pressure, temperature, and flow data during testing to help reactor developersanalyze and understand component performance in helium environment• Significance:••

He-CTF gives INL capabilities to test component prototypes in a non-irradiated, hightemperature, high-pressure, helium environment
Helium test loops exist in the U.S., but none are of this scale

Contact: Luke Voss (INL), luke.voss@inl.gov

MARVEL - Test Microreactor

Microreactor Application Research, Validation and EvaLuation Project

Key Design Features
Thermal Power

100 kW (85 kW nominal)

Electrical Power

20 kWe (QB80 Stirling Engines)

Weight< 12 US tonPrimary Coolant

Sodium-Potassium eutecticIntermediate Coolant

Lead

Coolant Driver

Natural Convection, single phase

Fuel

HALE(UZrH), 304SS clad, end caps

Moderator

HydrogenNeutron Reflector

Graphite, Beryllium (S200), Beryllium oxide

Reactivity Control

Radial Control Drums, Central AbsorberPrimary Coolant Boundary

SS316H

Innovation- MARVEL used an inherently safe research reactor fueland designed a high-temperature advanced reactor
Contact: Yasir Arafat (INL), Yasir.arafat@inl.gov

• The VTB supports NRIC’s mission of delivering successful
demonstration and deployment of advanced nuclear energy

How?
•••Library of Reference Model: database of advanced
multiphysics advanced reactor models that users can download,
edit, and re-run
Targeted Model Generation: developing demonstration-relevant
models (e.g., candidates for DOME/LOTUS) to accelerate safety
evaluations
Continuous Software QA: linking repository to softwaredevelopment to avoid legacy issues while enabling rapid codedevelopment

VTB So Far••••

30+ models hosted (and counting): 14 reactor designs, and 7 codes
showcased
Collaboration with NEAMS, industry, NRC, and academia
Help accelerate timelines for DOE/NRC confirmatory analysis
Accelerate development cycle for industry and academia

VTB Link: https://mooseframework.inl.gov/virtual_test_bed
NRIC Tech Talk Link: https://nric.inl.gov/nric-tech-talks-modeling_simulation/

Contact: Abdalla Aboujaoude (INL), abdalla.aboujaoude@inl.gov

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Accelerate
Licensing
Evaluation(NRC)

Accelerate
Authoriza-tion
Evaluation(DOE)

Accelerate
DesignMaturation(industry)

Targeted
Model
Generation

Library ofReference
ModelsTesting forAgile
Software QA

NRIC
VTB
VTB
Mission Mission Scope

Virtual Test Bed (VTB)

Reactor
Demonstrations

Questions?