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Full-core high-burnup BWR LOCA fuel performance analysis and FFRD susceptibility

Greenquist, Ian [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:000000021299065X)·Wysocki, Aaron [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000222043779)·Simon, Pierre-Clément A. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000170832628)·Sweet, Ryan [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]·Gamble, Kyle [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]·Asgari, Mehdi [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0009000236709970)·Hansen, Asher [Boise State Univ., ID (United States)]·Sarikaya, Baris [Constellation Energy Generation LLC, Kennett Square, PA (United States)]·Porter, Ian [Global Nuclear Fuel, Wilmington, NC (United States)]·Tusar, James [Constellation Energy Generation LLC, Kennett Square, PA (United States)]·Capps, Nathan [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)]·Salko, Jr., Robert [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000253566679)
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Abstract

The susceptibility of the boiling water reactor (BWR) Limerick Unit 1 to fuel fragmentation, relocation, and dispersal during a postulated large-break loss-of-coolant accident (LBLOCA) was calculated using a multiphysics framework. The simulations include full-core, rod-resolved neutronic, thermal hydraulic, and fuel performance models using the VERA, TRACE, and BISON codes. This work focused on the transient BISON simulations, which include both the normal operation and LBLOCA periods in the same simulations. Cladding integrity was assessed using two correlations that are included with BISON. make page break Several new BWR-specific features were recently added to BISON. This work represents the first time these features have been included in a core-scale set of simulations. This study hence evaluates the performance of these new models for an operating reactor with realistic operating conditions. Simulation results showed that cladding integrity was maintained (i.e., no rods burst). Finally, future work to improve BWR and PWR predictions using this framework is suggested.

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Greenquist, Ian [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:000000021299065X), Wysocki, Aaron [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000222043779), Simon, Pierre-Clément A. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000170832628), Sweet, Ryan [Idaho National Laboratory (INL), Idaho Falls, ID (United States)], Gamble, Kyle [Idaho National Laboratory (INL), Idaho Falls, ID (United States)], Asgari, Mehdi [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0009000236709970), Hansen, Asher [Boise State Univ., ID (United States)], Sarikaya, Baris [Constellation Energy Generation LLC, Kennett Square, PA (United States)], Porter, Ian [Global Nuclear Fuel, Wilmington, NC (United States)], Tusar, James [Constellation Energy Generation LLC, Kennett Square, PA (United States)], Capps, Nathan [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)], Salko, Jr., Robert [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000253566679). 2026-06-24. Full-core high-burnup BWR LOCA fuel performance analysis and FFRD susceptibility. https://doi.org/10.3389/fnuen.2026.1822290

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DOE OSTI2026

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DOE OSTI2026

Effect of spacer grids on high-burnup fuel fragmentation, relocation, and dispersal

Increasing the fuel burnup limit in light-water reactors to improve fuel cycle economics requires a strong technical foundation. Experimental observations from the Halden and Studsvik programs have revealed severe fuel fragmentation during loss-of-coolant accident (LOCA) conditions, highlighting the need for additional technical evaluation. Consequently, further LOCA test data are needed to complement existing findings and improve the understanding of fuel fragmentation, relocation, and dispersal (FFRD) behavior. Oak Ridge National Laboratory’s Severe Accident Test Station has played a significant role in advancing the understanding of high-burnup fuel fragmentation, relocation, and dispersal phenomena. One remaining gap in the available experimental database is the effect of fuel assembly structural features on cladding deformation behavior during a LOCA, and more specifically, their impact on the fuel’s ability to fragment, relocate, and disperse. Recent analyses using the BISON fuel performance code suggest that cladding deformation near grid spacers will remain below the 3% threshold that has been reported in the NRC Research Information Letter, indicating that the cladding could remain mechanically constrained during the LOCA event. This paper builds upon the BISON analyses to design and conduct a series of out-of-cell tests aimed at further evaluating cladding deformation in and around grid spacers. In addition, these tests were used to assess local cladding temperature conditions and compare them against analytical predictions in order to better replicate expected in-reactor behavior. Finally, an in-cell high-burnup LOCA test was designed and performed to evaluate the effects of a grid spacer, or cladding restraint, on fuel fragmentation, relocation, and dispersal susceptibility. The high-burnup test results differed from those of historical LOCA experiments, with a recorded rupture temperature of 861°C. Two ballooned regions and corresponding rupture openings were observed, with rupture widths of approximately 0.64 mm for both ruptures and rupture lengths of 4.8 mm and 5.6 mm, respectively.

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DOE OSTI2026

Identifying microstructures susceptible to pulverization in commercially irradiated high burnup UO2 under LOCA conditions

High burnup fuel fragmentation (HBFF) has been a concern in the nuclear industry for many years. When UO2 reaches and exceeds pellet average burnups around 55 GWd/tU, microstructural changes in the fuel pellet begin to occur that render the pellet susceptible to fine fragmentation under loss-of-coolant accident (LOCA) conditions. During a LOCA event, the cladding balloons and bursts, potentially releasing part of these fine fuel fragments into the reactor pressure vessel. This process is known as fuel fragmentation, relocation, and dispersal (FFRD). Presently, the US nuclear industry is developing a safety basis for FFRD with the goal of increasing burnups and pressurized water reactor cycle lengths. Increased cycle lengths would push the burnup limits of the fuel rods past the known threshold for HBFF susceptibility. In this work, the microstructural impact on HBFF was investigated by comparing the microstructures of as-irradiated rod segments to their post-LOCA tested counterparts. This investigation found that varied operational histories result in different microstructural evolutions across the pellet radius, which impacts the fragmentation behavior and radial location of the fragmentation. It is noted that regions with a high bubble density and a high density of grain boundaries fragment under LOCA-relevant conditions. In addition to the fragmentation that has been previously reported at the periphery of the fuel, fragmentation was also noted in the dark zone toward the fuel center. Analysis of the power histories of the fuel samples suggests that the dark zone forms in the central regions of the pellet between temperatures of approximately 740 and 960 °C.

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