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
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
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
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 2022.06 - Current
Bachelor of Science - Nuclear Engineering
Texas A&M University
College Station, TX 05.2019 - 2022.05
Bachelor of Arts - Chemistry And Engineering Physics
Augustana College
Rock Island, IL 08.2017 - 2019.05
Skills
Spent Nuclear Fuel Management and Analysis
undefinedTimeline
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 - 2022.05
Bachelor of Arts - Chemistry And Engineering Physics
Augustana College
08.2017 - 2019.05
Ph.D. - Nuclear Engineering
The University of Tennessee - Knoxville
2022.06 - 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.
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