Thermal-Hydraulics

Energy Research, Inc. has been involved in various thermal-hydraulics activities sponsored by the U. S. Nuclear Regulatory Commission (NRC), Office of Research, International Atomic
Energy Agency (IAEA), and Swiss Federal Nuclear Safety Inspectorate (ENSI) and others.

These activities include model development, code applications, development of Phenomena Identification and Ranking Tables (PIRTs), scaling, code assessment, and experimental benchmarking for operating plants and new reactors.

Examples of these programs include:

  • Experimental assessment of the TRACE computer code using:
    • The Ontario Hydro void fraction tests
    • The PANDA M9 and ISP42 tests
    • The Toshiba GIRAFFE integral test data
    • FIST
    • FRIGG
    • BFBT
    • Christensen
    • Westinghouse Model Boiler No. 2 (MB-2)
    • Oregon State University (OSU) Advanced Plant Experiment (APEX)
    • Japan Atomic Energy Research Institute (JAERI) Rig-of-Safety Assessment-V (ROSA-V)
  • Assessment of the heat and mass transfer analogy for prediction of steam condensation in the presence of non-condensable gases, and comparison to Westinghouse LST data
    (applicable to AP600 and AP1000).
  • Development of the technical basis and performance of TRACE code assessment in support of the U.S. EPR design certification activities.

    Energy Research, Inc. was recently awarded a contract to perform code improvements/ upgrading, perform code assessment, demonstrate code applicability for new designs, perform technical
    studies and provide support to maintained codes. Areas of support include:

    • The development of an ABWR TRACE model
    • Performance of pre- and post-test analyses for the PWR spent fuel pool experiments at SNL conducted under the Organization for Economic Development and Cooperation (OECD),
      Nuclear Energy Agency (NEA)
    • Support in assessment of TRACE applicability to iPWRs.