Design and full core fuel performance assessment of high burnup cores for 4-loop PWRs

Journal Article · Sun May 11 00:00:00 EDT 2025 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2025.105791· OSTI ID:2567076

Halimi, Assil ^[1]; Che, Yifeng ^[2]; Shirvan, Koroush ^[3]

---

1. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); MIT
2. Georgia Institute of Technology, Atlanta, GA (United States)
3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Increasing the fuel discharge burnup of current light water reactors (LWRs) promises reductions in fuel cycle and/or operations costs. By assuming a constant core power density, the economic gain is enabled by better fuel utilization and/or an increased capacity factor. In this effort to investigate greater than 62 MWd/kgU maximum rod average burnup for 110+ kW/l core power density, two core designs have been developed for a standard 17x17, 193 fuel assemblies pressurized water reactor (PWR). The levelized unit cost methodology is employed to evaluate fuel cycle, operation and maintenance, and capital cost impacts and to examine the economic viability of both core design pathways. Core design and optimization are performed using the commercial STUDSVIK code package. Fuel performance analysis is realized in full core configuration via auditing FRAPCON4.1, FAST1.2, and the high-fidelity code BISON. To provide a realistic assessment, the core design process takes into consideration best practices in current PWR core design. It features acceptable performance in terms of various core design constraints on maximum allowable peaking and boron concentration. Gadolinia (Gd2O3) is used as a burnable poison with a maximum of 9 wt% concentration while feeding 89 or 77 fuel assemblies in a 3-batch refueling scheme. Full core fuel performance simulation, which allows for characterization of relevant fuel temperatures, plenum pressures, stresses, and strains, is performed with respect to two bounding burnup levels. Such performance is potentially licensable for the 18-month high burnup core (<68 MWd/kgU peak pin), while it is more challenging for the 24-month high burnup core design pathway (<75 MWd/kgU peak pin). Maximum rod plenum pressure is identified as the most limiting fuel performance parameter. Here, while the scope of the present study focuses on the steady-state plus overpower conditions, the acceptability of the new discharge burnup has to be further assessed by considering uncertainties and impacts under accident scenarios in the future.

• Research Organization: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• Grant/Contract Number: AC07-05ID14517; NE0009212
• OSTI ID: 2567076
• Alternate ID(s): OSTI ID: 2565496
• Journal Information: Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Vol. 186; ISSN 0149-1970
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Core design
Full-core fuel performance
High burnup
LEU+ fuel
Nuclear economics
Nuclear fuel management