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Spent fuel pool boil-off experiments with high power and high time resolution

Schuster, C. & Stepanov, O. E., Apr 2025, In: Nuclear engineering and design. 435, 113958.

Research output: Contribution to journal › Research article › Contributed › peer-review

Posttest Calculations of Thermal-Hydraulic Conditions for Test Benches Simulating a Loss of Spent Fuel Pool Cooling Accident at BWR and VVER-1000/1200 Reactors

Ivanova, N. V., Bedretdinov, M. M., Stepanov, O. E., Karetnikov, A. G., Moisin, D. N. & Schuster, C., May 2024, In: Thermal engineering = Teploenergetika. 71, 5, p. 412-423 12 p.

Research output: Contribution to journal › Research article › Contributed › peer-review

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 journal › Research article › Contributed › peer-review

Safety cases for design-basis accidents in LWRs featuring passive systems

Mull, T., Wagner, T., Bonfigli, G., Buchholz, S., Schäfer, F., Schleicher, E. & Schuster, C. & 1 others, Sporn, M., Feb 2022, In: Nuclear engineering and design. 387, 13 p., 111095.

Research output: Contribution to journal › Research article › Contributed › peer-review

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 journal › Research article › Contributed › peer-review

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