Yunlin Xu
Engineering · Purdue University West Lafayette
Publications
127
Citations
1,072
Est. group size
~5
Recurring co-author estimate
Active years
32
Publishing since 1995
Yunlin Xu works on nuclear reactor physics and engineering, focusing on developing and improving computational methods for simulating how neutrons move and interact inside nuclear reactor cores (a process called neutron transport). This includes building faster, more parallelized simulation codes (such as PANDAS-MOC), improving numerical methods for reactor core modeling, and coupling neutron behavior with fuel and thermal-hydraulic (heat and fluid flow) simulations. Prospective students would likely work on high-performance computing methods applied to nuclear reactor simulation and fuel behavior modeling.
Publication output grew steadily from 2017 through a peak around 2021-2023, then has tapered off in the most recent two years.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Calculation and Verification of Geometry Parameters Integration in CSN Method Based on Quasi-Monte Carlo Method
Springer proceedings in physics · 2026
- Convergence Optimization of Curved Surface Nodal Method
Springer proceedings in physics · 2026
- Drn-Cskt: Solving Cold-Start in Knowledge Tracing with Disentangled Attention and Retentive Networks
SSRN Electronic Journal · 2025
- Curved surface nodal (CSN) method for the solution of neutron transport equation
Progress in Nuclear Energy · 2025
- Database of Atomic Mobility for Bcc Phase in the U–Zr Binary System
SSRN Electronic Journal · 2024
- A Neutronics-Fuel Coupling Model for the Simulation of Constituent Redistribution in U–Zr Fuel
SSRN Electronic Journal · 2024
- Advancements to Generalized Equivalence Theory for Preserving Cross Sections of Whole Core Simulations
SSRN Electronic Journal · 2024
- A neutronics-fuel coupling model for the simulation of constituent redistribution in U–Zr fuel
Progress in Nuclear Energy · 2024
- Advancements to generalized equivalence theory for preserving cross-sections of whole core simulations
Progress in Nuclear Energy · 2024
- Laser ignition of a GAP/ADN/AzBT mixture: ignition behavior
Journal of Physics Conference Series · 2024
- Hybrid parallel reduction algorithms for the multi-level CMFD acceleration in the neutron transport code PANDAS-MOC
Frontiers in Nuclear Engineering · 2023
- Additional axial decomposition parallelism for MOC solver in the neutron transport code PANDAS-MOC
Annals of Nuclear Energy · 2023
- Advancements to Generalized Equivalence Theory for Preserving Sections of Whole Core Simulations
SSRN Electronic Journal · 2023
- Parallel implementation of Red–Black ordering preconditioners for accelerating GMRES solutions in neutron transport code PANDAS-MOC
Annals of Nuclear Energy · 2023
- Fixed-Source Diffusion Solver in PARCS
Transactions of the American Nuclear Society · 2023
- Annals of Nuclear Energy×13
- Nuclear Science and Engineering×11
- SSRN Electronic Journal×9
- Transactions of the American Nuclear Society×9
- Progress in Nuclear Energy×4
- Muhammad Rizki Oktavian
Engineering · Purdue University West Lafayette
- Hussein Khalil
Engineering · Purdue University West Lafayette
- Dean Wang
Engineering · The Ohio State University
- Swapnil Morankar
Engineering · Purdue University West Lafayette
- Zuolong Zhu
Engineering · The Ohio State University
This profile was generated automatically from public scholarly data (OpenAlex). Group size and activity levels are estimates derived from co-authorship patterns.
Last updated Jul 20, 2026.
Claim or correct this profile