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Industry Positions Regulatory EngineerAcademic Articles Automated Multiphysics Evaluation Model Assessment and Determination of Thermal-Hydraulic Safety MarginsIndustry Positions Consulting EngineerIndustry Positions DevOps EngineerTeaching Positions Secondary School Technology & Design TeacherData Science Writings Imputing running economy over time dataEducation Teaching CertificateIndustry Positions Nuclear EngineerData Science Writings Creating and validating a continuous heat limited pace modelAcademic Articles Best-Estimate Plus Uncertainty Analysis for Continuous Energy Monte Carlo Coupled Neutron-Gamma Transport Simulations Through a 3-Loop Westinghouse PWR Concrete Biological Shield WallAcademic Articles Final Safety Evaluation for Topical Report 3002010613, “Benchmarks For Qualifying Fuel Reactivity Depletion Uncertainty—Revision 1” and Topical Report 3002010614, “Utilization Of the EPRI Depletion Benchmarks for Burnup Credit Validation—Revision 1” *Package*Academic Articles The History and the Future of Credibility Assessment Frameworks: from CSAU to EMDAP and BeyondAcademic Articles White Paper: Criticality Code Validation of Spent Fuel Pool Criticality Safety Analyses for ATF Fuel System Concepts with Greater Than 5% Enriched UraniumAcademic Articles Neutron Fluence Monitoring for Subsequent License RenewalAcademic Articles Case Studies Examining Spent Fuel Pool Criticality Uncertainty AnalysisAcademic Articles Mitigation Potential of Higher Burnup Fuel in Spent Fuel Pools with Uniform Neutron Absorber DegradationAcademic Articles Spent Fuel Pool K-Effective Sensitivity to Uniform Neutron Absorber DegradationAcademic Articles pySTATSAcademic Articles Benchmark on Sensitivity Calculation Academic Articles Development of an Efficient PENTRAN Model for Neutron Flux Simulation of the UFTR Shield TankEducation M.S., Nuclear EngineeringIndustry Positions InternIndustry Positions InternEducation B.S., Nuclear Engineering

Download a PDF of this CV

Language Skills

SCALE
MCNP
Python
R
Perl
Fortan
C++

Disclaimer

Made with the R package pagedown.

The source code is available on github.com/amritpatel/adpatelCV.

Last updated on 2024-08-08.

Main

Amrit Patel

Experienced nuclear engineer with a demonstrated history of working in federal nuclear safety regulation and advanced fission reactor development. Skilled in nuclear safety (radiation transport, criticality analysis, fuel performance, computer simulation validation, UQ) and computer programming.

Working on getting the first Oklo powerhouse lincensed.

Industry Experience

20242022

Regulatory Engineer

Oklo, Inc. Remote
  • Development of regulatory-facing technical products in the realm of safety analysis.
20222021

Consulting Engineer

NUMARK Associates, Inc. Remote
  • Commercial nuclear power plant licensing for an international regulatory authority.
  • Core physics methods verification and validation.
20222021

DevOps Engineer

Cherry Beam Games Remote
  • Implemented continuous integration using Git and setup a continuous deployment pipeline allowing for rapid and incremental game improvement for Bloxi on Steam.
  • A local Flask build server with a bit of Bash scripting was used to automate MacOS build signing and notarization alongside generation of valid builds for Windows and Linux.
  • Supported the lead developer’s vision of optimizing gameplay experience as the lead playtester.
  • Paved the path to more creative game modes such as the winnable “Daily Challenge Mode”.
  • Captured, edited, and produced gameplay trailers and GIFs for marketing purposes.
  • Designed and maintained a simple and clean business website hosted via Github Pages using Jekyll.
20192009

Nuclear Engineer

U.S. NRC, Office of Nuclear Reactor Regulation Rockville, MD
  • Principal contributor for topical report, license amendment request, and guidance development safety review teams, presenting information to mid-size audiences, mentorship of peers, explaining technical material to non-technical audiences (members of the public) and management, oversight of interns.
  • Planned/Conducted complex technical reviews in core nuclear engineering areas for the Offices of New Reactors and Nuclear Reactor Regulation (e.g., criticality, shielding, nuclear fuels, and method verication/validation) coordinating with project managers and technical staff in cross-cutting disciplines for several large projects (e.g., new reactor licensing, license renewal).
  • Proficient in safety evaluation reporting and confirmatory analysis including: Use of computer codes to perform simulations (e.g., SCALE code suite, MCNP, DAKOTA); complex data analysis using statistical software packages; use of various programming/scripting languages for software development, input/output processing, database management, and creating dynamic figures/reports/presentations.
  • Communication and reporting skills: Development and presentation of original research in support of NRC guidance development for various audiences (e.g., senior level management, ACRS, national/international conferences).
  • Collaboratively developed new guidance documents (e.g., spent fuel pool criticality safety and neutron fluence regulatory guides); NRC representative on ANS 19.10 standard committee.
  • Collaborated with international cohorts via participation in OECD/NEA Working Party on Nuclear Criticality Safety and associated expert groups including contributions to calculational benchmark reports.
2008

Intern

U.S. NRC, Office of New Reactors Rockville, MD
  • Assisted with the review of the GEH ESBWR CRB nuclear design lifetime. Supported audit activities, performed confirmatory analyses (using MonteBurns and MCNP5), and provided safety evaluation input.
  • Performed the acceptance review for the Levy Nuclear Plant, Units 1 and 2 combined license application.
2007

Intern

Southern Nuclear Operating Company Birmingham, AL
  • Worked with BWR core analysis engineers supporting Plant Hatch, Units 1 and 2.
  • Gained experience with CASMO-3/SIMULATE-3 via model implementation of a proposed CRB design; performed a study on the effect of the design on existing core.
  • Gained experience with GEH lattice physics codes working with bundle designs and control rod blade pattern development.

Education

2019

Teaching Certificate

TEACH-NOW Graduate School of Education Washington, D.C.
  • Secondary Computer Science
  • Secondary Mathematics
20092006

M.S., Nuclear Engineering

University of Florida Gainesville, FL
  • Thesis: Detailed Neutron Flux Characterization of the Experimental Shield Tank Facility at the UFTR. Research included modeling of the University of Florida Training Reactor using the 3-D deterministic discrete ordinates PENTRAN code to accurately characterize the neutron flux distribution within a surrounding experimental facility composed of water; code-to-code benchmarking was performed with MCNP5.
  • Served as teaching assistant for graduate level “Neutron Transport Theory” course. Duties included assisting students with coursework and grading assignments.
  • Received EIT certification.
20062002

B.S., Nuclear Engineering

University of Florida Gainesville, FL
  • Inducted into Alpha Nu Sigma Honor Society.
  • Member of American Nuclear Society (UF Chapter).

Teaching Experience

20202019

Secondary School Technology & Design Teacher

Lincoln School Kathmandu, Nepal
  • Taught courses for students to develop 21st century skills with an emphasis on information and communication technology literacy, media and internet literacy, data interpretation and analysis, computer programming through use of the design cycle of thinking, making, and refining (including troubleshooting, debugging, polishing).
  • Leader of the Technology and Innovation Curriculum Planning Committee charged with developing a school-wide technology and innovation philosophy, and looking at standards-based outcomes in order to design curriculum units.
  • Created a website hosted on Github Pages using Harvard’s CS50 curriculum to facilitate teaching computer science principles.
  • Started a student-led video production team to record, produce, and edit videos supporting various school events.
  • As the manager of this team, I also recorded, produced, and edited a miniseries documenting a community service project in the Chitwan region of Nepal where Grade 9 students along with myself and several other teachers worked on constructing two biogas digesters at neighboring sites.
  • Made several short films (“‘Exploratory’ Students Showcase of Season 2 Projects”; “Tiny Stage Series Fine Arts Edition, Theme: Water”).
  • Coordinated and led the live streaming of the South Asian Inter-Scholastic Association (SAISA) swimming tournament hosted at Lincoln School. This was the first time in SAISA history that a wireless in-field camera setup was used to capture live footage.
  • Led the filming of a special event at one of Nepal’s cherished ancient religious sites (also a UNESCO world heritage site) – Swayambhunath Stupa – in collaboration with the World Wildlife Fund and Decca/Universal Music Group in support of making resolutions with communities around the world calling for urgent action on the climate crisis.
  • Pioneered the use of drone video camera technology for sporting events as a means to identify areas of athlete and team improvement.

Selected Data Science Writing

2020

Imputing running economy over time data

Personal Blog
  • Creating custom R functions to treat missing data to visualize running economy data over time.
2019

Creating and validating a continuous heat limited pace model

Personal Blog
  • Using a trial and error approach, I create various multvariate regression models based on (temperature, humidity, pace) data points to see if I could come up with a continuous analytical formula for heat limited running pace as a function of temperature and humidity.
2015

Johns Hopkins University Data Science Specialization Coursework (online)

Rockville, MD
  • Statistical Inference
  • Regression Models
  • R Statistical Software Programming
  • Getting and Cleaning Data
  • Exploratory Data Analysis
  • Reproducible Research
2015

Fuel Modeling with SCALE Training

Rockville, MD
  • ORIGEN
  • ORIGAMI
  • Polaris
  • Sampler
2015

1st Workshop on Methodologies for SFP Simulations

Virginia Tech Arlington, VA
2015

Shielding Analysis Using SCALE/Monaco/MAVRIC

Rockville, MD
2015

Edward Tufte’s One-Day Course on “Presenting Data and Information”

Washington, D.C.
2014

Lattice Physics Analysis Using SCALE/Polaris and GenPMAXS

Rockville, MD
2014

Tennessee Industries Week: Nuclear Criticality Safety

University of Tennesssee Knoxville, TN
2013

SCALE Computational Methods for Burnup Credit, Including ISG-8 Revision 3

Rockville, MD
2012

ORNL Burnup Credit Validation Training Using SCALE6

Bethesda, MD
2011

TRACE/SNAP Advanced User Workshop

Potomac, MD
2011

Burnup Credit Workshop

Oak Ridge National Laboratory Knoxville, TN
2011

Shielding Analysis Using SCALE/MAVRIC

Rockville, MD
2010

HTGR Training Course

Rockville, MD
2010

TRACE/SNAP Computer Code Workshop

Potomac, MD
2009

SCALE Training Using ORIGEN-ARP/TRITON

Bethesda, MD
2009

OECD/NEA Workshop on Future Criticality Safety Research Needs

Pocatello, ID
2009

SCALE Training Using TSUNAMI/TSURFER/TSAR

Rockville, MD
2009

International OECD Halden Reactor Project Summer School

Halden, Norway
2009

FRAPCON/FRAPTRAN Fuel Performance Code Training

Richland, WA

Selected Publications

2024

Automated Multiphysics Evaluation Model Assessment and Determination of Thermal-Hydraulic Safety Margins

Proceedings of the Advanced Reactor Safety Conference Las Vegas, NV
  • Authored with Clyde Huibregtse and Patrick Everett
2019

Best-Estimate Plus Uncertainty Analysis for Continuous Energy Monte Carlo Coupled Neutron-Gamma Transport Simulations Through a 3-Loop Westinghouse PWR Concrete Biological Shield Wall

  • Simulation models based on previous neutron+photon transport code benchmarking study.
  • UQ studies to identify best methods to use with the FAVOR-DAKOTA code coupling project (e.g., LHS, PCE, PBA).
  • Authored FAVOR-DAKOTA UQ analysis tool to allow for inclusion of additional uncertainty parameters of interest when performing probabilistic fracture mechanics simulations.
  • FAVOR Fortran source code updated to allow running via command-line to allow coupling to DAKOTA.
  • The FAVDAKOTA utility was created as a simple user interface to setup (and launch) all of the necessary files for a successful FAVOR-PFM-DAKOTA run. FAVDAKOTA is currently designed to work with the following DAKOTA UQ method types: ‘random’, ‘lhs’, ‘wilks’, ‘pba’, ‘pce’.
2019
2018

The History and the Future of Credibility Assessment Frameworks: from CSAU to EMDAP and Beyond

Proceedings of the Best Estimate Plus Uncertainty International Conference: Multi-Physics Multi-Scale Simulations with Uncertainty Lucca, Italy
  • Authored with Josh S. Kaizer.
2017

Neutron Fluence Monitoring for Subsequent License Renewal

Proceedings of the 16th International Symposium on Reactor Dosimetry Sante Fe, NM
  • Authored with Joel Risner, Ben Parks, and Matthew Hardgrove.
2014
2014

pySTATS

  • An alternative to the USLSTATS utility packaged with SCALE.
2012

Benchmark on Sensitivity Calculation (Phase III)

Proceedings of PHYSOR 2012: Advances in Reactor Physics Linking Research, Industry, and Education Knoxville, TN
  • Authored with Tatiana Ivanova et al.
  • Served as the U.S. NRC representative for an international benchmarking effort.
2010

Development of an Efficient PENTRAN Model for Neutron Flux Simulation of the UFTR Shield Tank

Proceedings of PHYSOR 2010 Pittsburgh, PA
  • Authored with Alireza Haghighat.