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_bibliography/references.bib

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@article{seifert_delayed_2025,
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title={Delayed Neutron Precursor Group Parameter and Spectra Generation from Fast Fission of 235U in SCALE},
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author={Seifert, Luke and Betzler, Benjamin and Wieselquist, William and Jessee, Matthew and Munk, Madicken and Huff, Kathryn},
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journal={Nuclear Science and Engineering},
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pages={1--16},
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abstract={Delayed neutron precursor (DNP) group data are important for modeling reactor dynamics. Although the data for individual DNPs have been developed over time, the DNP group data present in the Evaluated Nuclear Data Files (ENDF) have not been updated in the past 20 years. In this work, we use SCALE to recreate the Godiva experiment that was used to generate the original DNP group structure for fast fission of 235U. However, each DNP is modeled using up-to-date data, and the results are then converted into a newly updated group structure. This conversion uses an iterative linear least squares solver to minimize chi-squared. The approaches used in this work also enable energy spectrum generation and uncertainty tracking. The method used in this paper for fast 235U fission DNP group structure updating can be applied to different energies and fissile nuclides. Demonstration of the uncertainty tracking in reactor kinetics and dynamics simulations is shown using point reactor kinetics simulations. Results show that there are data discrepancies between the International Atomic Energy Agency database and data used in ORIGEN, which are currently being fixed. Results also show that the proposed method for group spectra generation performs well.},
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year={2025},
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publisher={Taylor \& Francis}
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}
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@inproceedings{park_hybrid_2025,
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address = {Denver, CO},
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title = {A {Hybrid} {SN}-{Diffusion} {Method} for {Molten} {Salt} {Reactor} {Control} {Rod} {Modeling}},
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url = {https://www.ans.org/pubs/proceedings/article-58077/},
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doi = {doi.org/10.13182/MC25-47048},
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booktitle = {Proceedings of {The} {International} {Conference} on {Mathematics} and {Computational} {Methods} {Applied} to {Nuclear} {Science} and {Engineering} ({M}\&{C} 2025)},
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publisher = {American Nuclear Society},
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author = {Park, Sun Myung and Huff, Kathryn D and Munk, Madicken},
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month = apr,
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year = {2025},
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pages = {430--439}
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}
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@mastersthesis{yardas_implementation_2023,
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type = {Masters Thesis},

_data/alumni.yml

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name: Linkedin
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- name: Julia Roessler
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pic: /img/people/roesslerj.jmatthew-koziol/g
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pic: /img/people/roesslerj.jpg
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dates: 2019
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role: Undergraduate Research Assistant
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description: 'Julia was an undergraduate student at the University of Illinois who is eager to gain technical experience in the nuclear engineering field.'

_data/people.yml

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- name: Elijah Capps
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pic: /img/people/cappse.png
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dates: 2024-Present
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role: Undergraduate Research Assistant
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role: Graduate Research Assistant
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description: 'Eli started as an undergraduate in NPRE and is now a graduate research assistant interested in modeling nuclear energy systems.'
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social:
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- url: mailto:[email protected]
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icon: github-alt
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name: Github
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- url: https://www.linkedin.com/in/bryan-park-11a6b32b4/
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icon: linkedin
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name: LinkedIn
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- name: Thomas Bohnert
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icon: github-alt
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name: Github
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- name: Amanda Schultz
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pic: /img/people/schultza.png
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dates: 2025-Present
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role: Undergraduate Research Assistant
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description: 'Amanda is an undergraduate in MechSE interested in advanced computation and nuclear power as a sustainable energy solution.'
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social:
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- url: mailto:@[email protected]
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icon: envelope-o
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name: Email
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- url: https://github.com/amandas36
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icon: github-alt
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name: Github
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- name: You
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pic: /img/people/you.png
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dates: now

_data/presentations.yml

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- title: "A Hybrid SN-Diffusion Method for Molten Salt Reactor Control Rod Modeling"
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presenter: Sun Myung Park
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event: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
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type: Technical Presentation
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place: Denver, CO
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month: April
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day: 28
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year: 2025
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pic: '/img/pres/2025-mc.png'
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slides: '/pres/2025-park-mc.pdf'
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description: "This presentation presents a hybrid SN-diffusion method for
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accurate modeling of control rods in time-dependent molten salt reactor
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simulations. The hybrid method combines the strengths of both approaches by
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applying transport corrections generated using the SN method near control
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rods. 1-D simulation results show that the hybrid method provides improved
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rod worth estimates compared to pure diffusion models. The hybrid method
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iterative scheme demonstrates robustness in convergence and converges rapidly
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within two outer iterations."
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- title: "Useful practices in open-source software development for nuclear science and engineering"
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presenter: Oleksandr R. Yardas
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event: American Nuclear Society Student Conference

img/people/schultza.png

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img/pres/2025-mc.png

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papers/seifert_delayed_2025.pdf

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pres/2025-park-mc.pdf

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