Computational modeling demonstrates an optimized high-load MOX fuel design in boiling water reactors, suggesting reduced surplus plutonium and streamlined transition to fast reactors.
Key Points
To develop and evaluate a high-plutonium-loading boiling water reactor fuel assembly concept to prevent plutonium accumulation prior to the commercialization of fast reactors.
Adapted a commercial 10 × 10 lattice assembly into a water-rod-free configuration with optimized partial-length rods to enhance plutonium loading while preserving normal pressure drop levels.
Evaluated a full mixed-oxide (MOX) core design utilizing plutonium recovered from spent uranium dioxide fuel after 30 years of cooling.
The full-MOX core model achieved an annual plutonium loading of 3.3 t-Pu/year, an operating cycle length of 24 months, and a discharge burnup of 45 GWd/t.
Spent MOX fuel preserved a transuranic-equivalent fissile fraction of 0.44 for approximately 100 years, facilitating future fast-reactor reuse and reducing reprocessing requirements.