Mr. Geoffrey Beausoleil
Material Scientist
Nuclear Science & Technology
Idaho National Laboratory

Abstract

The Advanced Test Reactor (ATR) has successfully been used for the testing of fast reactor fuel for nearly two decades. Numerous fuel designs for a variety of fast reactor applications have been tested and the results from these experiments have been shown to be consistent with examinations of used fuel rods obtained from actual fast reactors. Despite these successes, significant challenges for testing fast reactor fuel in ATR include the following: (1) ATR coolant temperatures are roughly 50 C, while outlet temperatures for fast reactors are often 500 C or higher; (2) the thermal spectrum reduces dose rates to the cladding and can result in non-prototypical distributions of fission rates within the fuel; (3) the use of a helium-filled gap between the test fuel rod and the capsule serves to raise cladding temperature but the small gap distance can make the experimental conditions sensitive to fabrication tolerances; (4) changes in anticipated power levels (driven by other experimental needs) within the ATR can result in undesirable temperatures; and (5) power levels within the test fuel rods are such that achieving high burnup can take on the order of a decade. A revised irradiation methodology has been put forth to address these needs through the Advanced Fuels Campaign (AFC) Fission Accelerated Steady-state Test (FAST). The first round of these tests have been completed at Idaho National Laboratory (INL) with tests focused on the irradiation of alloy fuel forms for use in sodium fast reactors. Tests included the use of fuel additives (Sn, Sb, and Pd) for reducing the gettering of lanthanide fission products, zirconium liners to mitigate fuel-cladding chemical interaction, and annular fuel geometry for sodium-free fuel designs. The initial non-destructive PIE has been completed and includes visual inspection, precision gamma scanning, and neutron radiography of the FAST rodlets.

Biography

Geoffrey Beausoleil, commonly known as Boone, is a staff scientist within the Fuel Design and Development Department in NS&T. His current projects include leading the AFC-FAST irradiation experiments, leading and contributing to multiple LDRDs, and serving as the technical lead for testing and characterization in AMMT. His involvement is primarily in the development of accelerated methods of irradiation experiments and post-irradiation characterization.

His past experience includes work in refueling and plant overhaul of aircraft carriers and submarines in the NNPP. He has also performed research on ceramic membranes for gas separation and fuel cells as well as development of dilute magnetic semi-conductor nano materials for both magnetic memory applications and cancer therapies.

Thursday, February 17. 2022
4:00 pm seminar

Hybrid Option  (Speaker is remote)

zoom (link upon request)
or
Room 1202 Burlington Labs