Multi-Cycle Core Design Optimization with Multiple Input and Output Constraints

Aaron M. Graham, Benjamin S. Collins, Dave Kropaczek

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

This paper presents a novel multicycle optimization framework designed to address the complexities of high burnup fuel (HBu) fuel deployment in light-water reactors (LWRs). HBu offers substantial economic benefits by enabling either longer operational cycles or reduced fuel requirements, thus lowering operational costs. However, the deployment of HBu introduces significant design challenges, including increased core reactivity constraints, heightened power peaking, and thermal design margin requirements, particularly for scenarios involving elevated enrichments and multicycle fuel management. To tackle these challenges, this study uses OPTIX, an advanced optimization tool that integrates uses parallel simulated annealing and APEX for reactor physics calculations. This paper presents initial results for multi-cycle optimizations with OPTIX. Results are presented for a single-cycle optimization and a two-cycle optimization. The core layout and possible assemblies are specified via user input, along with input and output constraints that must be satisfied. Both problems were able to be solved by OPTIX to generate a minimized total fuel cost. All input and output constraints were also satisfied by the optimized solutions. Several areas of improvement are identified as a result of these initial optimization calculations that can be implemented in OPTIX moving forward.

Original languageEnglish
Title of host publicationProceedings of Advances in Nuclear Fuel Management, ANFM 2025
PublisherAmerican Nuclear Society
Pages286-296
Number of pages11
ISBN (Electronic)9780894482267
DOIs
StatePublished - 2025
Externally publishedYes
Event2025 Advances in Nuclear Fuel Management, ANFM 2025 - Clearwater Beach, United States
Duration: Jul 20 2025Jul 23 2025

Publication series

NameProceedings of Advances in Nuclear Fuel Management, ANFM 2025

Conference

Conference2025 Advances in Nuclear Fuel Management, ANFM 2025
Country/TerritoryUnited States
CityClearwater Beach
Period07/20/2507/23/25

Funding

This material is based upon work supported by the U.S. Department of Energy Small Business Innovative Research program under Award Number DE-FOA-0003202. Calculations were performed on the Sawtooth high-performance computer at INL which is supported for the VERA Users Group (https://vera.ornl.gov) by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517. This work was supported by Microsoft Azure credits provided through the "Microsoft for Startups Founders Hub." The resources and infrastructure made available by Microsoft have significantly facilitated the development and implementation of the coupled simulation capabilities presented in this study. We extend our gratitude for their support in advancing research and innovation in nuclear reactor technology.

Keywords

  • core design
  • core optimization
  • fuel performance

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