Abstract
After several years of relatively low activity in the field of Light Water Reactor (LWR) fuel
development, the Department of Energy again began to engage in developing new fuel technologies
and irradiation performance data prompted by the Fukushima Daichi nuclear accidents. New
competencies for irradiation testing in material test reactors in the United States began to be
developed at this time using the Advanced Test Reactor (ATR), High Flux Isotope Reactor (HFIR),
Massachusetts Institute of Technology Reactor (MITR), and the Transient Reactor Test Facility
(TREAT). Capsules for testing fuel and cladding materials in ATR and HFIR were deployed, a
Pressurized Water Reactor (PWR) condition loop for testing fuel rods was established in ATR,
cladding corrosion studies were performed using a water loop in MITR, and TREAT pulse testing
capabilities were commissioned for fuel rods in water capsules. The more recent and unexpected
closure of the Halden Boiling Water Reactor (HBWR) also prompted further investments in Loss
of Coolant Accident (LOCA) testing capabilities at TREAT. New configurations of these test
devices show further potential in enhanced steam condition control and other investigations are
building toward a flowing water loop for testing transient to dryout conditions. The closure of
HBWR also prompted a major project currently underway to construct additional water loops in
ATR where a novel approach is being pursued to enable Boiling Water Reactor (BWR) conditions.
A meaningful collaborative project was awarded to MITR which, amidst an unexpected major
overhaul of the reactor, has expanded cladding corrosion test capabilities at MITR. New
explorations have led to methods for unique experiments at HFIR including channel box
irradiations. New device developments are also bridging toward future potential for instrumented
capsule irradiation tests in ATR and HFIR. Finally, a new project referred to as the System Physics
Advanced Reactor Critical facility (SPARC) is gaining traction towards a large zero-power reactor
able to produce physics validation data for LWR fuel bundle designs with increased enrichment and
enhanced absorbers for 24-month operation cycles. This paper provides a brief summary of the
status of these irradiation testbed capabilities with an emphasis on current efforts toward future
capabilities to obtain new data and maximize the performance potential of LWR fuel technologies.
development, the Department of Energy again began to engage in developing new fuel technologies
and irradiation performance data prompted by the Fukushima Daichi nuclear accidents. New
competencies for irradiation testing in material test reactors in the United States began to be
developed at this time using the Advanced Test Reactor (ATR), High Flux Isotope Reactor (HFIR),
Massachusetts Institute of Technology Reactor (MITR), and the Transient Reactor Test Facility
(TREAT). Capsules for testing fuel and cladding materials in ATR and HFIR were deployed, a
Pressurized Water Reactor (PWR) condition loop for testing fuel rods was established in ATR,
cladding corrosion studies were performed using a water loop in MITR, and TREAT pulse testing
capabilities were commissioned for fuel rods in water capsules. The more recent and unexpected
closure of the Halden Boiling Water Reactor (HBWR) also prompted further investments in Loss
of Coolant Accident (LOCA) testing capabilities at TREAT. New configurations of these test
devices show further potential in enhanced steam condition control and other investigations are
building toward a flowing water loop for testing transient to dryout conditions. The closure of
HBWR also prompted a major project currently underway to construct additional water loops in
ATR where a novel approach is being pursued to enable Boiling Water Reactor (BWR) conditions.
A meaningful collaborative project was awarded to MITR which, amidst an unexpected major
overhaul of the reactor, has expanded cladding corrosion test capabilities at MITR. New
explorations have led to methods for unique experiments at HFIR including channel box
irradiations. New device developments are also bridging toward future potential for instrumented
capsule irradiation tests in ATR and HFIR. Finally, a new project referred to as the System Physics
Advanced Reactor Critical facility (SPARC) is gaining traction towards a large zero-power reactor
able to produce physics validation data for LWR fuel bundle designs with increased enrichment and
enhanced absorbers for 24-month operation cycles. This paper provides a brief summary of the
status of these irradiation testbed capabilities with an emphasis on current efforts toward future
capabilities to obtain new data and maximize the performance potential of LWR fuel technologies.
| Original language | American English |
|---|---|
| Title of host publication | TopFuel 2025: Nuclear Reactor Fuel Performance Conference |
| DOIs | |
| State | Published - Oct 5 2025 |
INL Publication Number
- INL/CON-25-83129
- 207138