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Benjamin Betzler is a seasoned nuclear engineer with expertise in reactor physics, research, and Monte Carlo simulations. He has worked at top institutions, including Oak Ridge National Laboratory and University of Michigan, and holds a Ph.D. in Nuclear Engineering and Radiological Sciences from the University of Michigan.

Experience

  • Radiant
    • Los Angeles Metropolitan Area
    • Head of Nuclear Engineering
      • Oct 2022 - Present
      • Los Angeles Metropolitan Area

    • United States
    • Research Services
    • 700 & Above Employee
    • Senior R&D Staff; Group Leader
      • Oct 2020 - Sep 2022

      ◦ Served as deputy director of the SCALE code system, managing analysis scope and products to ensure quality and consistency with research direction.◦ Collaborated on the Kairos Hermes pebble-bed reactor severe accident analysis and review assessment with the SCALE-MELCOR analysis toolset.◦ Collaborated on NEAMS Shift and Griffin radiation transport and reactor physics applications to molten salt reactor (MSR) designs to demonstrate workflows.◦ Directed and developed a research group focused on pushing world-leading science in research and advanced reactor physics design and analysis.◦ Directed the DOE-NE Transformational Challenge Reactor Program, coordinating with industry and regulatory partners to demonstrate additive manufacturing technologies.◦ Coordinated iterative design and analysis of High Flux Isotope Reactor (HFIR) low-enriched uranium (LEU) cores, incorporating fabrication and qualification feedback.◦ Advised on molten salt reactor source term analyses and Lagrangian plug flow modeling with the SCALE/TRITON and SCALE/ORIGEN tools.

    • R&D Staff
      • Jan 2019 - Oct 2020

      ◦ Led the design and analysis thrust of the DOE-NE Transformational Challenge Reactor Program, collaborating with material science, facility & licensing, and reactor design staff to deploy a nuclear reactor using additive manufacturing technologies.◦ Collaborated in an interlaboratory effort to analyze Molten Salt Breeder Reactor dose and define specifications for a Molten Salt Reactor Experiment transient benchmark.◦ Developed reactor physics and fuel cycle models of the Molten Salt Demonstration Reactor for safeguards, source term, off gas system, and isotope production analyses.◦ Collaborated on advanced low-enriched uranium dispersion fuel design optimization and analyses with Shippingport reactor fuel.◦ Advised on development and deployment of automated optimization tools for High Flux Isotope Reactor (HFIR) fuel design.◦ Advised on the implementation of neural networks for fuel cycle simulation, ORIGEN reactor library interpolation, and accelerating inverse depletion methods.◦ Led high-fidelity as-built reactor physics analysis in support of HFIR fuel characterization and operations.

    • Associate R&D Staff
      • May 2016 - Dec 2018

      ◦ Led a multidisciplinary team of nuclear and mechanical engineers to design a reactor built using advanced manufacturing techniques.◦ Led a multi-laboratory effort to develop the DOE-NE Molten Salt Reactor Campaign modeling and simulation plan, communicating with industry, academia, laboratory staff, and leadership in other DOE-NE programs.◦ Calculated fuel salt content and developed models of molten salt reactor fueling, storage, and processing systems for safeguards characterization and analysis.◦ Developed molten salt reactor neutronics and fuel cycle analysis tools for the SCALE code package, leading the integration in ORIGEN, NEWT, and TRITON.◦ Coordinated the modeling and simulation effort of the DOE-NE Molten Salt Reactor Campaign, supporting dose estimation, dynamic modeling, and chemistry modeling.◦ Developed design optimization tools and performed design studies of a HFIR low-enriched uranium core with the Shift Monte Carlo tool.◦ Collaborated with Transatomic Power Corporation to perform neutronic and fuel cycle analysis and design optimization for their molten salt reactor design.

    • Postdoctoral Research Associate
      • May 2014 - Apr 2016

      ◦ Performed depletion and criticality analysis of boiling water reactor spent fuel assemblies with different operating conditions for burnup credit analysis.◦ Performed core design and analysis of a prismatic fluoride salt–cooled advanced demonstration reactor concept using Serpent and PARCS.◦ Developed tools and performed neutronic analysis for fast and thermal spectrum molten salt reactors to characterize them for the fuel cycle options campaign.◦ Designed a small nuclear rocket engine using accident tolerant fuel in KENO and performed optimization studies on packing fractions, fuel loads, and core geometry.◦ Performed depletion simulation, neutronic analysis, and developed Python scripts in support of the HFIR LEU conversion program and HFIR operations.◦ Tested the depletion and lattice physics performance of SCALE modules (TRITON, Polaris, NEWT, and KENO) for light water reactor geometries.◦ Developed a Python script and built TRITON inputs to automatically generate the 1,470 ORIGEN cross section libraries released with updated versions of SCALE.

  • University of Michigan
    • Greater Detroit Area
    • Graduate Student Research Assistant & Instructor
      • Sep 2008 - Apr 2014
      • Greater Detroit Area

      ◦ Simulated the Fort St. Vrain (FSV) gas-cooled reactor with MCNP, using RELAP5 to analyze thermal feedback. Wrote Python scripts for writing and updating MCNP and RELAP5 inputs.◦ Modeled ~20 FSV pulsed neutron and other startup experiments with MCNP and performed sensitivity studies on design parameter uncertainties.

  • Los Alamos National Laboratory
    • Santa Fe, New Mexico Area
    • Graduate Research Assistant
      • Jun 2012 - Aug 2012
      • Santa Fe, New Mexico Area

      ◦ Wrote a research Monte Carlo code in MATLAB to calculate alpha eigenvalues and eigenfunctions of infinite media using a transition rate matrix method akin to the fission matrix method. This method improves upon the k-alpha iteration in MCNP.

  • Oak Ridge National Laboratory
    • Knoxville, Tennessee Area
    • Graduate Research Assistant
      • Jun 2010 - Aug 2010
      • Knoxville, Tennessee Area

      ◦ Calculated heat deposited in the HFIR reactivity control system with MCNP to investigate causes of control cylinder clad corrosion, spalling, and failure.◦ Analyzed the burnup of control cylinder absorbers and cladding with ORIGEN and determined the axial heat flux distribution with simple heat transfer models.

  • P2 Energy Solutions
    • San Antonio, Texas Area
    • GIS Technician (Summer)
      • 2006 - 2007
      • San Antonio, Texas Area

Education

  • 2010 - 2014
    University of Michigan
    Doctor of Philosophy (Ph.D.), Nuclear Engineering and Radiological Sciences
  • 2008 - 2010
    University of Michigan
    Master of Science in Engineering, Nuclear Engineering and Radiological Sciences
  • 2005 - 2008
    University of Michigan
    Bachelor of Science in Engineering, Nuclear Engineering and Radiological Sciences

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Industry Focus. “Nuclear Energy”

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