PhD Thesis
UQ of Monte Carlo XS Generation for HTRs
Ann Arbor, MI
Advised by Prof. Thomas Downar
Aug 2023
- Thesis title: Quantification and Minimization the Uncertainty Propagation of Monte Carlo Cross Section Generation for HTR Applications
- Developed an analytic UQ methods based on perturbation theory for UQ of MC generated XS, implemented in AGREE
- Developed a stochastic UQ methods based on randomly sampling for UQ of MC generated XS, implemented with Dakota, coupled with AGREE and SAM
- Monte Carlo-Deterministic hybrid methods for HTR neutronics analysis, SAM system code for thermal-hydraulics simulation
- Methods were demonstrated on HTR-10 steady-state benchmark and gFHR steady-state / transient simulations
- UQ
- MC XS
- Hybrid method
- HTR
Experience
University of Michigan
Ann Arbor, MI
Postdoctoral Research Assistant
Sept 2023 - Current
- Developed a gFHR multi-physics system model to train a Digital Twin surrogate using the VARMAX data-driven stochastic regression model
- Over 4000x sppedup for the reactor simulation using data-driven machine learning algorithms
- Decreasing the O&M cost and improving the economic efficiency of the advanced reactors
- Developed visualization apps for user interaction and display over 40 Digital Twin predicted state variables
- Python
- C++
- MatLab
Argonne National Laboratory Summer Intern
Lemont, IL
Graduate Research Aid
May 2022 - Aug 2022
- SAM code development using C++ and MOOSE framework, implemented a control rod module with spacial effect
- Implemented a numerical ODE solver to solve xenon/iodine Bateman equations
- Created demo cases and unit tests for the newly implemented module/solver
- gFHR neutronics/thermo-fluids modeling and simulation
- C++
- MatLab
- Python
Research
RSOR - Linear Solver Preconditioner
- Implemented RSOR (Reduced Successive Over Relaxation) preconditioner for banded matrices, improving run time by ~25%
- The method was applied in the numerical library Futility to improve the performance of linear solvers
- C++
- Fortran
lpCMFD
- Implemented a linear prolongation approach to accelerate the convergence of CMFD (Coarse Mesh Finite Difference) solver by ~30% iterations, the stability was also improved
- The algorithm was applied in reactor simulation code MPACT
- Fortran
Projects
gFHR Modeling and Simulations
- Fluoride-cooled High-temperature Reactor (FHR), pebble-bed based design
- Monte Carlo - Deterministic Hybrid Method with Serpent 2 code and AGREE code
- Coupled neutronics / thermo-fluids simulation of the core and primary/secondary loops using system analysis code SAM
- Model development for the Digital Twin (DT) training
MSRE
- Molten Salt Reactor Experiment modeling and simulation
- Neutronics simulation using hybrid method with Serpent/Shift and PARCS
SPERT
- Development of the transient capability for the NEAMS neutronics code PROTEUS
- Modeling and Simulation of the SPERT experimental benchmark
Publications
- Jasmin Lim, et al. A Hybrid Surrogate Modeling Framework for the Digital Twin of a Fluoride-salt-cooled High-temperature Reactor (FHR). Nuclear Engineering and Design (2024)
- Jin Li, et al. Uncertainty Propagation of Monte Carlo Cross-Section Generation for Graphite-Moderated Pebble Bed Reactors. Nuclear Science and Engineering (2024)
- Jin Li, et al. Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor. Nuclear Technology (2024)
- Kaitlyn Barr, et al. Verification of AGREE and Serpent for the Steady State HTR-10 Benchmark Problems. PHYSOR (2022)
- Jin Li, et al. Neutronics and Thermal-Hydraulics Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (gFHR). PHYSOR (2022)
- Jin Li, et al. Neutronics Simulation of the Molten Salt Reactor Experiment with Serpent/Shift and PARCS. Mathematics & Computation (2021)
- Jin Li, et al. Demonstration of a Linear Prolongation CMFD Method on MOC. PHYSOR (2020)
- Yugao Ma, et al. Neutronics and thermal-hydraulics coupling analysis in accelerator-driven subcritical system. Progress in Nuclear Energy (2020)
- Won Sik Yang, et al. Development of Transient Capabilities for the NEAMS Neutronics Code PROTEUS. NEUP report DOE-PUR-0008561 (2019)
- Ishita Trivedi, et al. Impact of Nuclear Data Uncertainties on Lead-cooled Fast Reactor Simulations. Best Estimate Plus Uncertainty (2018)
- Yiran Wang, Jin Li. Research on the Monte Carlo Simulation Methods of ADS MYRRHA. Reactor Physics Asia (2017)
- Xiaotong Shang, et al. Subcritical Multiplication Factor and Burnup Analysis of ADS with RMC. ANS Winter Meeting (2017)
References
Brendan Kochunas
(PhD Committee Member) Assistant Professor at University of Michigan
Dan O'Grady
(Internship Supervisor) Research Assistant at Argonne National Laboratory
Jin Li
- +1 (734) 834-4826
- [email protected]
- https://www.linkedin.com/in/jinli-io/
- https://jinli.io/en
- https://github.com/jin-li
- Ann Arbor, MI
Profile
PhD grad (Aug 2023) major in nuclear engineering. Interested in advanced nuclear reactor design, multi-physics coupled analysis, reactor physics code development, applying AI/ML on nuclear engineering. Seeking positions for nuclear engineering research.
Diplomas
- Doctor of Philosophy (2023)
- Nuclear Engineering and Radiological Sciences
- GPA = 3.926
- University of Michigan, Ann Arbor
- Bachelor of Engineering (2018)
- Engineering Physics
- Tsinghua University, China
Skills
- Reactor Simulation Code
- Serpent
- MCNP
- VERA
- PARCS
- OpenMC
- SAM
- AGREE
- MPACT
- SCALE
- MOOSE Framework
- Programming
- C++
- Python
- MATLAB
- Fortran
- C
- Bash/Zsh
- Developer Tools
- Linux system
- Git
- Docker
- Conda
- CMake/XMake
- Misc
- LaTeX
- Markdown
- Microsoft Office
- Adobe Tools
Interests
- Tennis
- Ski
- Cooking
- Building website