Interdisciplinary Fuels and Materials

    Project: Research

    Project Details

    Description

    The INFLAME project consists of modelling and experiments current and advanced nuclear fuel, both in normal operation and accident conditions. The main part of the project focuses on nuclear fuel modelling, as data from integral experiments is obtained from international research programmes. The fuel behaviour module FINIX will be developed further in the project, validated and application range broadened. On the experimental side, advanced claddings will be investigated on their mechanical and oxidation behaviour. As a first step in Finland, experimental studies on the behaviour fuel pellets in in-reactor conditions will be performed with simulant materials. The project consists of three work packages: Integral fuel behaviour (FINIX development, RIA modelling, review of advanced and accident tolerant fuels), experimental studies on advanced cladding materials (mechanical properties, hot loop experiments, steam furnace oxidation testing) and experimental studies on fuel pellet materials (construction of equipment and microscopy). As nuclear fuel provides the first safety barriers against the spread of fission products, the understanding of its behaviour is important for nuclear safety. The applicability of FINIX in LOCA conditions will be improved and codes used for safety analysis of Finnish reactors will be validated further as well as models developed for these codes. New information on the performance of advanced claddings will be obtained and experimental capability on fuel pellet studies at VTT will be increased.
    AcronymINFLAME
    StatusActive
    Effective start/end date1/01/19 → …

    Research Output

    • 4 Conference article in proceedings
    • 1 Article

    Implementation of burnup effects in the multiphysics fuel behavior module FINIX

    Loukusa, H., Peltonen, J., Valtavirta, V. & Tulkki, V., 1 Feb 2020, In : Annals of Nuclear Energy. 136, 107022.

    Research output: Contribution to journalArticleScientificpeer-review

  • Advanced cladding materials for accident tolerant fuels

    Heikinheimo, J., Huotilainen, C., Pohja, R., Ivanchenko, M. & Loukusa, H., 31 Oct 2019, SYP2019 Proceedings. Finnish Nuclear Society, 4 p.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Open Access
  • Coolant-cladding interaction models in FINIX fuel behaviour module

    Peltonen, J. & Loukusa, H., 31 Oct 2019, SYP2019 Proceedings. Finnish Nuclear Society, 5 p.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Open Access