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Multiphysics Simulation of the NASA SIRIUS-CAL Fuel Experiment in the Transient Test Reactor Using Griffin

Author

Listed:
  • Tian Jing

    (Nuclear Design Discipline, TerraPower, Bellevue, WA 98005, USA
    Formerly of Idaho National Laboratory, Idaho Falls, ID 83415, USA.)

  • Sebastian Schunert

    (Reactor Physics Methods and Analysis, Idaho National Laboratory, Idaho Falls, ID 83415, USA)

  • Vincent M. Labouré

    (Reactor Physics Methods and Analysis, Idaho National Laboratory, Idaho Falls, ID 83415, USA)

  • Mark D. DeHart

    (Reactor Physics Methods and Analysis, Idaho National Laboratory, Idaho Falls, ID 83415, USA)

  • Ching-Sheng Lin

    (Nuclear Design Discipline, TerraPower, Bellevue, WA 98005, USA
    Formerly of Idaho National Laboratory, Idaho Falls, ID 83415, USA.)

  • Javier Ortensi

    (Reactor Physics Methods and Analysis, Idaho National Laboratory, Idaho Falls, ID 83415, USA)

Abstract

After approximately 50 years, NASA is restarting efforts to develop nuclear thermal propulsion (NTP) for interplanetary missions. Building upon nuclear engine tests performed from the late 1950s to the early 1970s, the present research and testing focuses on advanced materials and fabrication methods. A number of transient tests have been performed to evaluate materials performance under high-temperature, high-flux conditions, with several more experiments in the pipeline for future testing. The measured data obtained from those tests are being used to validate the Griffin reactor multiphysics code for this particular type of application. Griffin was developed at Idaho National Laboratory (INL) using the MOOSE framework. This article describes the simulation results of the SIRIUS-CAL calibration experiment in the Transient Reactor Test Facility (TREAT). SIRIUS-CAL was the first transient test conducted on NASA fuels, and although the test was performed with a relatively low core peak power, the test specimen survived a temperature exceeding 900 K. Griffin simulations of the experiment successfully matched the reactor’s power transient after calibrating the initial control rod position to match the initial reactor period. The thermal-hydraulics model largely matches the time-dependent response of a thermocouple located within the experiment specimen to within the uncertainty estimate. However, the uncertainty range is significant and must be reduced in the future.

Suggested Citation

  • Tian Jing & Sebastian Schunert & Vincent M. Labouré & Mark D. DeHart & Ching-Sheng Lin & Javier Ortensi, 2022. "Multiphysics Simulation of the NASA SIRIUS-CAL Fuel Experiment in the Transient Test Reactor Using Griffin," Energies, MDPI, vol. 15(17), pages 1-28, August.
  • Handle: RePEc:gam:jeners:v:15:y:2022:i:17:p:6181-:d:897744
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    Cited by:

    1. Ruslan Irkimbekov & Alexander Vurim & Galina Vityuk & Olzhas Zhanbolatov & Zamanbek Kozhabayev & Artur Surayev, 2023. "Modeling of Dynamic Operation Modes of IVG.1M Reactor," Energies, MDPI, vol. 16(2), pages 1-20, January.

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