TAG 2.2 Fuel and reactor physics
DECAPOD – Deterministic safety analyses with Kraken, VTT
Research reports:
Lauranto, U., Valtavirta, V. 2024. Evaluating the performance of the GenPoly group constant model with the CBH benchmark. VTT Research Report, VTT-R-00336-24. 19 p.
Valtavirta, V. 2024. BWR group constant generation models for the CBH benchmark. VTT Research Report, VTT-R-00091-24. 8 p.
Ketola, V-A. 2023. Group constant state point generation and fit goodness evaluation tools for KrakenTools. VTT Research Report, VTT-R-00512-23. 20 p.
Conference papers and journal articles:
Komu, R., Tuominen, R., Valtavirta, V. 2023. Coupling TRACE with VTT’s Fuel Solver SuperFINIX for Transient Analysis. M&C 2023 – International Conference on Mathematics and Computation Methods Applied to Nuclear Science and Engineering, 13-17 August 2023, Niagara Falls, Canada. https://cris.vtt.fi/en/publications/coupling-trace-with-vtts-fuel-solver-superfinix-for-transient-ana
Lauranto, U., Komu, R., Rintala, A., Valtavirta, V. 2023. Validation of the Ants-TRACE code system with VVER-1000 coolant transient benchmarks. Annals of Nuclear Energy Volume 190, 15.9.2023, 10p. https://doi.org/10.1016/j.anucene.2023.109879
Tuominen, R., Valtavirta, V. 2023. Hybrid Mesh Based Predictions of Rod Level Thermal Margins. M&C 2023 – International Conference on Mathematics and Computation Methods Applied to Nuclear Science and Engineering, 13-17 August 2023, Niagara Falls, Canada. https://cris.vtt.fi/en/publications/hybrid-mesh-based-predictions-of-rod-level-thermal-margins-149
Valtavirta, V., Bilodid, Y. 2023. Critical Spectrum Burnup Calculations with Serpent Monte Carlo Code. M&C 2023 – International Conference on Mathematics and Computation Methods Applied to Nuclear Science and Engineering, 13-17 August 2023, Niagara Falls, Canada. https://cris.vtt.fi/en/publications/critical-spectrum-burnup-calculations-with-serpent-monte-carlo-co
Valtavirta, V., Rintala, A. 2023. Validating Kraken for VVER-1000 fuel cycle simulation using the X2 benchmark. Annals of Nuclear Energy Volume 190. 14 p. https://doi.org/10.1016/j.anucene.2023.109878
MATFINE – Methods for current and accident tolerant fuels modelling, VTT
Research reports:
Peltonen, J., 2024, Initial implementation of cladding ballooning model in FINIX fuel performance code. VTT Research Report, VTT-R-00238-24. 14 p.
Toivonen, A., Lukin, J., Peltonen, S. 2024. Sample plugging tests for Accident Tolerant Fuel cladding steam exposures. VTT Research Report, VTT-R-0065-24. 17 p.
Pohja, R. 2024. Biaxial creep test of DIN 1.4790 cladding material. VTT Research Report, VTT-R-00085-24. 11 p.
Arkoma, A. 2024. Cromium coated cladding behaviour in RIA situations – a literature review. VTT Research Report,VTT-R-00105-24. 17 p.
NOTCO – Neutronics for fuel outside the reactor core, VTT
Research reports:
Vaara, L. 2025. Development of cross section uncertainty propagation methodology for Monte-Carlo code Serpent 2.2. VTT Research Report, VTT-R-00075-25. 16 p.
Kähkönen, T. 2024. Spent nuclear fuel inventory calculations with a micro-depletion model. VTT Research Report, VTT-R-00469-24. 16 p.
Conference papers and journal articles:
Rochman, D. et al. 2024. An introduction to spent nuclear fuel decay heat for light water reactors: a review from the NEA WPNCS. EPJ Nuclear Sciences and Technologies, Volume 10, 2024. https://doi.org/10.1051/epjn/2024010