Lam Ba Hoang Nguyen
Graduate Research Assistant
Knoxville,TN
Summary
Motivated, detail-oriented Graduate Student currently pursuing doctorate degree in Nuclear Engineering with 3 years of research experience focused on computational simulation for reactor analysis and spent fuel management. Adept at constructing simulation models and well-versed in creating efficient programs to conduct, optimize and evaluate research experiments with multiple input parameters. Strong commitment towards increasing knowledge and advancing experiences in a research environment. Striving to foster skills and pursue new positions that offers professional challenges utilizing interpersonal skills, excellent time management and problem-solving skills.
Overview
3
3
years of professional experience
11
11
years of post-secondary education
Work History
Used Fuel Management Intern
Idaho National Laboratory
Idaho Falls, ID
05.2024 - Current
- Designed, investigated and evaluated feasibility for transportation, storage and disposal of 2 types of DOE-managed spent nuclear fuel in standardized canisters.
- Developed simulation model and performed criticality analysis for over 10 potential degradation scenarios of waste forms and disposal package internal components.
- Documented and reported analysis and results in engineering calculations and analysis reports with aims for publications.
- Gained hands-on experience in various software programs, increasing proficiency and expanding technical skill set.
- Contributed to positive team environment by collaborating with fellow colleagues on multi-disciplinary research projects.
Graduate Student Research Assistant
Dr. Ivan Maldonado
Knoxville, TN
06.2022 - Current
Current Research: Viability evaluation for containment of commercial and advanced spent nuclear fuel forms in standardized canister as part of a transportation, storage and disposal system.
- Designed and evaluated containment configuration of various spent fuel forms from commercialized and advanced reactors in standardized canisters.
- Developed intact and potential degraded configurations of the waste forms proposed for long-term disposal.
- Performed evaluations for different configurations to compare against established safety requirements for fuel storage in confinement casks.
- Documented research methods and obtained results in academic papers aimed for publication.
- Met regularly with research team to present research progress and discuss future objectives.
Undergraduate Research Assistant
Texas A&M Department Of Nuclear Engineering
College Station, Texas
05.2021 - 05.2022
Main Research: Radiation Transport Calculations using NJOY Nuclear Data Processing System ( June 2021 - Spring 2022)
- Generated isotopic multi-group microscopic cross-section using NJOY Nuclear Data Processing System to calculate macroscopic cross section for composite atoms.
- Developed MCNP models for particle flux and energy deposition for infinite and non-infinite medium problems.
- Developed Python programs and special formulas to produce neutron and photon energy spectrum using NJOY multi-group XS with MCNP data as benchmark for statistical analysis.
- Obtained reduction of generation time by 300% on average while maintaining statistical error below 5% in comparison with MCNP.
- Collaborated to identify relevant questions and determine best methods of enhancing precision and computational efficiency.
Education
Ph.D. - Nuclear Engineering
The University of Tennessee - Knoxville
Knoxville, TN 06.2022 - Current
Bachelor of Science - Nuclear Engineering
Texas A&M University
College Station, TX 05.2019 - 05.2022
Bachelor of Arts - Chemistry And Engineering Physics
Augustana College
Rock Island, IL 08.2017 - 05.2019
Skills
Spent Nuclear Fuel Management and Analysis
Python Programming
Criticality Safety Analysis
Advanced Modeling and Simulation using SCALE
MCNP Neutronic Simulation
Reactor System Analysis with CASMO and Simulate3
Timeline
Used Fuel Management Intern
Idaho National Laboratory
05.2024 - Current
Graduate Student Research Assistant
Dr. Ivan Maldonado
06.2022 - Current
Undergraduate Research Assistant
Texas A&M Department Of Nuclear Engineering
05.2021 - 05.2022
Bachelor of Science - Nuclear Engineering
Texas A&M University
05.2019 - 05.2022
Bachelor of Arts - Chemistry And Engineering Physics
Augustana College
08.2017 - 05.2019
Ph.D. - Nuclear Engineering
The University of Tennessee - Knoxville
06.2022 - Current
Publications
1) Feasibility Analysis for Packaging Sodium-Cooled Fast Reactor (SFR) Spent Nuclear Fuel in Existing Canister Designs (Spring 2023 - Spring 2024 )
- Utilized resourcefulness in finding publicly available information to construct and simulate a SFR core through its fuel cycle using SCALE TRITON.
- Analyzed model validity by comparing reactor performance metrics and end-of-cycle (EOC) fuel isotopics to reported SFR values at similar power levels.
- Performed criticality evaluation for potential containment methods of both fresh and depleted nuclear fuel and compared results against established criticality requirements for fuel storage in confinement casks.
- Documented and presented research efforts at 2024 Waste Management Symposia.
2) In-Package Criticality Evaluation for Packages Containing Graphite Spent Nuclear Fuel in DOE Standard Canisters (June 2022 - Spring 2023)
- Reconstructed canister models fully loaded with spent nuclear fuels from Peach Bottom 2 (PB2) and Fort Saint Vrain (FSV) reactors.
- Utilized MCNP to perform criticality evaluation of storage configurations for fuels in their intact and possible degraded forms, including scenarios with water intrusion.
- Determined compliancy with criticality upper safety limit (USL) for intact configurations of DOE Standard Canisters loaded with PB2 and FSV spent nuclear fuel.
- Construct models for potential degradation of PB2 fuels to compare against safety standards on criticality and proposed potential mitigation methods for outlier scenarios.
- Documented research methods and presented results at ANS 2023 Summer conference.