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## Education
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* Ph.D. Nuclear Engineering, Oregon State University, In progress
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* Ph.D. Nuclear Engineering, Oregon State University, 2024
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* B.S. Nuclear Engineering, University of Florida, 2019
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## Biography
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Kayla Clements is a graduate student and research assistant at Oregon State University under Dr. Todd Palmer. Prior to starting at Oregon State, Kayla worked as a reactor physics intern at Idaho National Laboratory developing MCNP models for the Transient Reactor Test Facility, and as a national nuclear data center intern at Brookhaven National Laboratory automating data generation using EMPIRE.
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Dr. Kayla Clements is a graduate Oregon State University (advisor Dr. Todd Palmer). Prior to starting at Oregon State, Kayla worked as a reactor physics intern at Idaho National Laboratory developing MCNP models for the Transient Reactor Test Facility, and as a national nuclear data center intern at Brookhaven National Laboratory automating data generation using EMPIRE.
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Dr. Clement's PhD research was directly affiliated with CEMeNT.
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* Exascale Software Engineering
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* Predictive Science
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We are lead by Dr. Todd Palmer (Oregon State University) with researchers in nuclear engineering, computer science, software engineering, mechanical engineering, computational physics, and mathematics who are supported by eight graduate students. So far, work related to and funded by the center has resulted in two PhD, three MS, and one Honors BS, with many more to come.
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We are lead by Dr. Todd Palmer (Oregon State University) with researchers in nuclear engineering, computer science, software engineering, mechanical engineering, computational physics, and mathematics who are supported by eight graduate students. So far, work related to and funded by the center has resulted in four PhDs, four MSs, and one Honors BSs, with many more to come.
*[E. Lamé](../members/ethan_lame), [C. J. Palmer](../members/camille_palmer), [T. S. Palmer](../members/todd_palmer), [I. Variansyah](../members/ilham_variansyah), [R. G. McClarren](../members/ryan_mcclarren/). Post-processing Results From a Monte Carlo Neutron Transport Code Using Compressed Sensing. To appear in *International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (ANS M&C 2025).* Denver, CO, USA.
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*[J. P. Morgan](../members/joanna_morgan/), [B. Cuneo](../members/braxton_cuneo/), [I. Variansyah](../members/ilham_variansyah), [K. E. Niemeyer](../members/kyle_niemeyer). Enabling GPU portability into the Numba-JITed Monte Carlo particle transport code MC/DC. (2025). To appear in *International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (ANS M&C 2025).* Denver, CO, USA. Preprint DOI [10.48550/arXiv.2501.05440](https://doi.org/10.48550/arXiv.2501.05440).
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*[B. Cuneo](../members/braxton_cuneo/), [J. P. Morgan](../members/joanna_morgan/), [I. Variansyah](../members/ilham_variansyah), [K. E. Niemeyer](../members/kyle_niemeyer). Comparing the Performance of MC/DC's on-GPU Event-based Processing Methods in Multigroup and Continuous-energy Problems. To appear in *International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (ANS M&C 2025).* Denver, CO, USA.
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*[B. Cuneo](../members/braxton_cuneo/) and [I. Variansyah](../members/ilham_variansyah). “An Alternative to Stride-Based RNG for Monte Carlo Transport.” In
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Transactions of The American Nuclear Society, volume 130 (1), pp. 423–426 (2024). DOI [10.13182/T130-44927](https://doi.org/10.13182/T130-44927)
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*[V. Novellino](../previous_members/vincent_novellino) and [D. Anistratov](../members/dmitriy_anistratov), Analysis of Hybrid MC/Deterministic Methods for Transport Problems Based on Low-Order Equations Discretized by Finite Volume Scheme. *Transaction of American Nuclear Society*, v. 130, 2024 [Preprint DOI: 10.48550/arXiv:2403.05673](doi.org/10.48550/arXiv.2403.05673)
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*[I. Variansyah](../members/ilham_variansyah/), [J. P. Morgan](../members/joanna_morgan/), [J. Northrop](../members/jordan_northrop)[K. E. Niemeyer](../members/kyle_niemeyer/), and [R. G. McClarren](../members/ryan_mcclarren/). “Development of MC/DC: a performant, scalable, and portable Python-based Monte Carlo neutron transport code.” In *International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering*. Niagara Falls, Ontario, Canada (2023). Preprint DOI [10.48550/arXiv.2305.13555](https://doi.org/10.48550/arXiv.2305.13555).
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# Dissertations and Theses
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*[Kayla Beth Clements](../members/kayla_clements/). . Ph.D. dissertation. School of Nuclear Science and Engineering, Oregon State University, Corvallis, OR, USA. December 2024.
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*[Benjamin Joseph Whewell](../previous_members/ben_whewell). Hybrid Numerical Methods and Solution Verification for the Neutron Transport Equation. Ph.D. dissertation. Dept. Aerospace and Mechanical Engineering, University of Notre Dame, South Bend, IN USA. November 2024. [online](https://curate.nd.edu/articles/dataset/Hybrid_Numerical_Methods_and_Solution_Verification_for_the_Neutron_Transport_Equation/27927858?file=51111842)
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*[Alexander Mote](../members/alex_mote). Neurons for Neutrons: A Transformer Model for Computation Load Estimation on Domain-Decomposed Neutron Transport Problems. Masters of Science Thesis. School of Computer Science and Engineering, Oregon State University, Corvallis, OR USA. May 30 2024. [online](https://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/gx41ms56m)
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*[Samual Passman](../members/sam_passman). Development of the iterative-Quasi-Monte Carlo (iQMC) Method for Neutron Transport Simulations. Ph.D. dissertation. Department of Aerospace and Mechanical Engineering, University of Noter Dame, South Bend, IN, USA, 2024
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*[Samual Passman](../members/sam_passman). Development of the iterative-Quasi-Monte Carlo (iQMC) Method for Neutron Transport Simulations. Ph.D. dissertation. Department of Aerospace and Mechanical Engineering, University of Notre Dame, South Bend, IN, USA, 2024. [online](https://curate.nd.edu/articles/dataset/Development_of_the_Iterative_Quasi-Monte_Carlo_iQMC_Method_for_Neutron_Transport_Simulations/25607787)
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*[Jordan Northrop](../members/jordan_northrop). Variance Reduction for Time-Dependent Monte Carlo Neutron Transport. Masters of Science Thesis, School of NSE, Oregon State University, Corvallis, OR 2024
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