Modeling, analysis, and optimization of complex nuclear processes and facilities via computational methods: The HALEU process case study

Journal Article · 07 December 2023 · Progress in Nuclear Energy

DOI: https://doi.org/10.1016/j.pnucene.2023.104993 · OSTI ID:2367530

Garcia, Humberto E.  ^[1]; Patterson, Michael N. ^[1]; Carlson, Reed B. ^[1]

---

1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Improving and adapting industrial systems to timely meet changing programmatic and market demands is an important goal to achieve, including when operating and maintaining complex nuclear processes and facilities. However, changes to these complex systems are costly, particularly when they are already in place and bounded to stringent requirements and constraints such as when handling radioactive material and contaminated equipment. These conditions often exist when treating spent nuclear fuel remotely within shielded nuclear radiation chambers, commonly referred as hot cells, to condition nuclear material and/or fabricate products for utilization in other nuclear enterprises such as in the manufacture of advanced nuclear fuel. The illustrative case considered here is the production of high assay low enriched uranium (HALEU) products supporting the deployment of advanced nuclear reactors. For the HALEU program, resources invested were and are being systematically analyzed so that these investments are maximized in a facility that is nearly 60 years old. A methodology that has effectively enabled optimized and improvements in the Spent Fuel Treatment (SFT) program, and consequently the HALEU program, involves discrete event simulation as addressed in this article. Here, the quantification of multiple productivity metrics, including material processing rates, cycle times, bottlenecks, number of material transfers as well as equipment, workstation, and material handling utilization, has resulted in a myriad of diverse discoveries and data-informed decisions regarding process layout and constituent, labor levels and schedules, selection of new process units, storage needs, and other critical process configurations. This article describes such a computational capability being applied for decision-making, illustrates its application to an actual process and program, provides illustrative results, and argues how computational methods for the modeling, analysis, and optimization of complex processes and facilities does lead to informed decisions derived from data and not only from intuition.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC07-05ID14517
• OSTI ID: 2367530
• Report Number(s): INL/JOU--23-75706-Rev000
• Journal Information: Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Vol. 167; ISSN 0149-1970
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English