Development and validation of fuel performance codes (POKEVA): POKEVA summary report

Seppo Kelppe

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Abstract

Advancements in updating, improving, and extending of fuel performance codes in use at VTT have been accomplished. Continuing effort to introduce a probabilistic transient analysis tool has resulted in a concept of core-wide assessment that will be used to estimate the number failing rods in an accident. Steady-state codes have been further validated. Selected models have been critically reviewed. In addition to uranium dioxide, doped pellets, inert matrix fuel and thorium dioxide fuel have been studied. Development efforts at VTT are being combined with similar programmes through international collaboration. Vital training of young experts urgently required to compensate personnel turnover has continued.
Original languageEnglish
Title of host publicationSAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010
Subtitle of host publicationInterim Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages99-111
ISBN (Print)978-951-38-7266-3, 978-951-38-7267-0
Publication statusPublished - 2009
MoE publication typeNot Eligible

Publication series

SeriesVTT Tiedotteita - Research Notes
Number2466
ISSN1235-0605

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  • Cite this

    Kelppe, S. (2009). Development and validation of fuel performance codes (POKEVA): POKEVA summary report. In SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report (pp. 99-111). VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2466 http://www.vtt.fi/inf/pdf/tiedotteet/2009/T2466.pdf