*Experiments funded by Nuclear Science User Facilities (NSUF)
**Experiments funded by other DOE programs, such as NERI, NEET, NEUP, GAIN, SBIR, STTR etc.
| Experiment Title | Environment | In-Service | Purpose of Experiments |
|---|---|---|---|
| Advanced Manufacturing Fuel Irradiation (AMFI) | Fuel capsules at 650 °C (in 3GV6) | 2020 | Verifying the integrity of novel ceramic fuel compacts created using advanced manufacturing techniques by monitoring production of fission product gasses |
| Thermo-Electric Generator Irradiation (TEGI) | Inert gas at 500 °C | 2020 | To generate electrical energy in-core using solid-state thermo-electric devices, and to monitor the performance in real-time during irradiation |
| Thermal Conductivity Probe Irradiation (TCP)* | Inert gas, 360 °C | 2019 | Irradiation testing of advanced thermal conductivity measurement instrumentation |
| Advanced Cladding Irradiation (ACI)-Accidental Tolerant Fuel (ATF) Phase 2b** | Water, 290 °C | 2019 | Corrosion and bond testing of SiC/SiC composite, and coated Zircaloy materials for accident tolerant fuel/advanced clad applications in PWRs – Westinghouse-led program |
| U of Pittsburgh Fiber Optic Experiment (PFOX) | Inert gas, 600-650 °C | 2019 | Performance testing of multiple ultrasonic and fiber optic sensors under irradiation in inert gas. |
| Fluoride Salt 4 (FS-4)Graphite Reflector | Inert gas, 700 °C | 2018 | Tritium permeation measurements with and without the presence of liquid lithium flouride-beryllium fluoride salt, and test of tritium barrier coating for the High Temperature Fluoride Salt Reactor. Also demonstrated the use of a “graphite vertical” position outside the core for high temperature neutron irradiations. |
| TREAT Instrumentation Tests | Atmospheric air, 50 °C, Reactor power <100 kW, steady state and transient power conditions | 2017, 2018 | Transient Test Reactor (TREAT) instrumentation tests: neutron and gamma detectors including newly developed micro-pocket fission detectors with flux wires for benchmarking |
| Advanced Cladding Irradiation (ACI)-Accidental Tolerant Fuel (ATF) Phase 2** | Water, 290 °C | 2017-2018 | Corrosion and bond testing of SiC/SiC composite, coated Zircaloy, and 3D printed alloy materials for accident tolerant fuel/advanced clad applications in PWRs – Westinghouse-led program |
| ULTRA 2* | Inert gas, 450 and 750 °C | 2017 | Performance testing of multiple ultrasonic and fiber optic sensors under irradiation in inert gas |
| ACI-Shared Irradiation** | Water, 290 °C | 2017 | Corrosion and bond testing of samples duplicating the HYCO test matrix (samples with n and γ exposure, γ exposure, and coolant exposure only) plus samples from Ceramic Tubular Products |
| Hybrid Composite (HYCO) ATF Clad Irradiation | Inert gas, 350 °C | 2016 | Irradiation of a large set of candidate high performance LWR clad materials for post-irradiation property testing |
| Fluoride Salt 3 (FS-3)** | Inert gas, 700 °C | 2016 | Tritium transport measurements on SiC/SiC and graphite samples irradiated in liquid lithium fluoride-beryllium fluoride salt for the High Temperature Fluoride Salt Reactor. Samples from U.S. DOE program and Chinese Academy of Sciences |
| In-core Crack Growth Monitoring* | Water, 290 °C | 2016 | Demonstration of actively loaded crack growth sample with real time crack length monitoring |
| Fluoride Salt 2 (FS-2)** | Inert gas, 700 °C | 2014 | Corrosion and tritium transport measurements on SiC/SiC and metal coupons irradiated in liquid lithium fluoride-beryllium fluoride salt for the High Temperature Fluoride Salt Reactor IRP |
| ACI-Accidental Tolerant Fuel Phases 1A, 1B (ATF)** | Water, 290 °C | 2014-2016 | Corrosion and bond testing of SiC/SiC composite, coated Zircaloy and “hybrid” clad samples for accident tolerant fuel applications in PWRS – Westinghouse-led program |
| ACI-BWR** | Water, 290°C | 2013-2014 | Corrosion and creep testing on SiC/SiC BWR channel box coupons under BWR core conditions |
| ULTRA* | Inert gas, 430 °C | 2013-2014 | Performance testing of multiple magnetostrictive and piezoelectric ultrasonic sensors under irradiation in inert gas |
| Fluoride Salt 1 (FS-1)** | Inert gas, 700 °C | 2013 | Corrosion and tritium transport measurements on SiC/SiC and metal coupons irradiated in liquid lithium fluoride-beryllium fluoride salt for the High Temperature Fluoride Salt Reactor IRP |
| LUNA 2 (In-Core Sample Assembly – ICSA)** | Inert gas, 800 °C | 2012 | Follow-on to LUNA 1 at higher temperature |
| LUNA 1 (ICSA)** | Inert gas, 500 °C | 2012 | Evaluation of irradiation damage in fiber optic sensors manufactured by Luna Innovations Inc. for use as in-core temperature monitors |
| Hydride Fuel* | Inert gas, 400 °C (clad) | 2011-2012 | Irradiation of novel liquid-metal bonded uranium-zirconium hydride fuel rods in Zircaloy-4 cladding for Light Water Reactor (LWR) applications |
| High-T ICSA irradiation of “Max Phases” ** | Inert gas, 300 – 800 °C | 2010-2011 | Irradiation of five different ternary carbides and nitrides of Ti for post-irradiation evaluation of properties with possible applications in high temperature gas reactors |
| Mo-99 Irradiation | Inert gas (~400 °C) | 2010 (Pilot) | Evaluate thermal neutron activation (n, γ) production of Mo-99 |
| High Temperature In-core Sample Assembly (ICSA)* | Inert gas, to 900 °C | 2010 | Evaluate thermal design of capsule incorporating “gamma susceptor” for passively heated irradiations up to 900 °C |
| ACI* | Water, 290 °C | 2009-2012 | Continued irradiation of tubing samples with addition of bonding specimens to evaluate end-cap bond processes |
| ACI | Water, 290 °C | 2009 | Continued irradiation of clad tubing samples from previous ACI with addition of next generation, smaller diameter tubing |
| ACI** | Water, 290 °C | 2006-2007 | Investigation of corrosion and mechanical property behavior of triplex SiC/SiC composite clad tubing under PWR conditions |
| High Temperature Irradiation Facility (HTIF) | Inert gas, 800 – 1600 °C | 2005-2006 | Irradiation of SiC/SiC composites and surrogate TRISO fuel particles |
| Electrochemical Corrosion Potential (ECP) | Water, 290 °C | 2004 | ECP measurement of in-core coolant and oxides to investigate mechanisms of shadow corrosion |
| Shadow Corrosion 2 | Water, 290 °C | 2004 | Phase 2 of 1999 Shadow Corrosion Loop |
| Annular Fuel** | Inert gas, 300 °C (clad) | 2004 | Demonstration of vibro-packed, internally and externally cooled annular fuel under irradiation and test of manufacturing process |
| Alumina Fiber Composite Clad** | Water, 295 °C | 2000 | Test of alumina-based ceramic fiber composites as potential cladding material under PWR conditions |
| Shadow Corrosion 1 | Water, 290 °C | 1999 | Test clad samples with various counter materials and gaps under BWR conditions to investigate shadow corrosion |
| Sensor Irradiation | Water, 290 °C | 1994 | Test in-vessel detectors for Electrochemical Corrosion Potential (ECP) and crack growth rate and investigate crack arrest by hydrogen water chemistry |
| Irradiation-Assisted Stress Corrosion Cracking (IASCC) | Water, 290 °C | 1990 | Test effects of coolant chemistry on Irradiation Assisted Stress Corrosion Cracking (IASCC) of BWR alloys |
| BWR Coolant Chemistry Loop | Water, 290 °C | 1990 | Evaluate effect of chemical additives on N-16 carryover and benchmark radiolysis codes for Boiling Water Reactors (BWR) |
| PWR Coolant Chemistry Loop | Water, 320 °C | 1989 | Measure effect of pH on corrosion product transport and ex-core radionuclide deposition to optimize Pressurized Water Reactor (PWR) chemistry specifications |