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4 Results for: "Nuclear Technology, Nuclear Process Technology"

Research output (3)

  1. Analysis of uncertainties for results of experiment with boiling-off the coolant simulation using SOCRAT-B1/B2-code for spent fuel pool conditions

    Bedretdinov, M. M., Pantyushin, S. I., Stepanov, O. E., Melikhov, O. I. & Schuster, C., Jun 2023, In: Nuclear engineering and design. 407, 112271 p., 112271.

    Research output: Contribution to journalResearch articleContributedpeer-review

    Published
  2. KORSAR/GP and SOCRAT/V1 codes’ validation for the loss of cooling at spent fuel pool conditions

    Bedretdinov, M. M. (First author), Stepanov, O. E., Sledkov, R. M. & Schuster, C., 2 Aug 2021, In: Nuclear Engineering and Design. 375, 375, 111089.

    Research output: Contribution to journalResearch articleContributedpeer-review

    Published
  3. Thermal hydraulic analysis of the convective heat transfer of an air-cooled BWR spent fuel assembly

    Partmann, C. (First author), Schuster, C. & Hurtado Gutierrez, A., 2018, In: ATW - Internationale Zeitschrift fur Kernenergie. 63, 6/7, p. 397-400

    Research output: Contribution to journalResearch articleContributedpeer-review

    Published

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