Nuclear Engineering and Technology (Mar 2023)

Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment

  • L. Luzzi,
  • T. Barani,
  • B. Boer,
  • A. Del Nevo,
  • M. Lainet,
  • S. Lemehov,
  • A. Magni,
  • V. Marelle,
  • B. Michel,
  • D. Pizzocri,
  • A. Schubert,
  • P. Van Uffelen,
  • M. Bertolus

Journal volume & issue
Vol. 55, no. 3
pp. 884 – 894

Abstract

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Design and safety assessment of fuel pins for application in innovative Generation IV fast reactors calls for a dedicated nuclear fuel modelling and for the extension of the fuel performance code capabilities to the envisaged materials and irradiation conditions. In the INSPYRE Project, comprehensive and physics-based models for the thermal-mechanical properties of U–Pu mixed-oxide (MOX) fuels and for fission gas behaviour were developed and implemented in the European fuel performance codes GERMINAL, MACROS and TRANSURANUS. As a follow-up to the assessment of the reference code versions (“pre-INSPYRE”, NET 53 (2021) 3367–3378), this work presents the integral validation and benchmark of the code versions extended in INSPYRE (“post-INSPYRE”) against two pins from the SUPERFACT-1 fast reactor irradiation experiment. The post-INSPYRE simulation results are compared to the available integral and local data from post-irradiation examinations, and benchmarked on the evolution during irradiation of quantities of engineering interest (e.g., fuel central temperature, fission gas release). The comparison with the pre-INSPYRE results is reported to evaluate the impact of the novel models on the predicted pin performance. The outcome represents a step forward towards the description of fuel behaviour in fast reactor irradiation conditions, and allows the identification of the main remaining gaps.

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