Linsen Li

Linsen Li

Assistant researcher

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  • Timeline

  • About me

    State Power Investment Corporation Leading Engineer, Technical Director of Nuclear Energy and Technology Research Institute

  • Education

    • Tsinghua University

      2006 - 2012
      Doctor of Philosophy (Ph.D.) Nuclear Engineering
    • Tsinghua University

      2002 - 2006
      Bachelor Nuclear engineering and technology
  • Experience

    • Tsinghua University

      Aug 2006 - Jan 2012
      Assistant researcher

      Study on the basic coupling method of neutronics and T-H, including the way of coupling, the cross section update and the transient coupling scheme, and basic coupling approach based on the CFD code CFX; Research on the coupling method of MCNP5 and CFX based on a single fuel rod model and a 3×3 rod bundle model; Research on the coupling of MCNP5 and CFX based on a Pebble Bed-Advanced High Temperature Reactor (PB-AHTR) validated compared with the results of the coupling of MCNP5 and RELAP5-3D.

    • Politecnico di Torino

      Sept 2008 - Dec 2008
      Exchange student

      Succeeded to accomplish the research on pulse source experiment facility and develop a reactor core simulator for the facility.

    • UC Berkeley

      Apr 2009 - Mar 2010
      Visiting scholar

      Succeeded to establish the neutronics and thermal-hydraulics core models of the next generation nuclear power plant, PB-AHTR, using MCNP and RELAP5 and develop the interface code using PERL script language to complete the coupled calculation. Completed the core model development and reactor physics design of a experimental reactor FHR-16 using MCNP.

    • University of Michigan

      Apr 2010 - Jan 2011
      Research scholar

      Succeeded to develop a steady-state thermal-hydraulic solver - PATHS for the US NRC reactor core simulator PARCS, and couple PATHS into PARCS. Completed the verification and validation work for PARCS/PATHS.

    • State Power Investment Corporation Research Institute

      Jun 2012 - now

      Research on Gen III NPP design verification, safety analysis and assessment such as CAP1400 designed by SNPTC, SMR Concept design and safety analysis such as Compact SMR of SNPTC, Gen IV and new concept reactors design and verification such as Lead or LBE Cooled Fast Reactor (LFR) designed by SPICRI, thorium-based molten salt reactor (TMSR) designed by SINAP, advanced simulation research and application including coupling of thermal-hydraulics and neutronics.

      • Techinical Director of Nuclear Energy and Technology Research Institute

        Jun 2024 - now
      • Deputy Director (Chair) of Science and Technology Management Department

        Sept 2021 - Jun 2024
      • Deputy Director of Nuclear Energy and Nuclear Technology Research Institute

        Mar 2021 - Aug 2021
      • Deputy Director (Chair) of Reactor Theory Research Disivion

        May 2019 - Mar 2021
      • Principal Engineer

        Dec 2017 - May 2019
      • Senior Engineer

        Jun 2012 - Dec 2017
  • Licenses & Certifications

    • Registered Nuclear Safety Engineer