Improvements in transient fuel performance modelling

Arttu Knuutila, Jaakko Miettinen, Jan-Olof Stengård

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

Abstract

VTT employs the fuel transient performance code FRAPTRAN for safety-related analyses of nuclear fuel. Within the High-burnup Upgrades in Fuel Behaviour Modelling research task (KORU), capabilities of FRAPTRAN have been improved by coupling the fuel performance code to an advanced thermal hydraulic model GENFLO. Further, the mechanical modelling in the FRAPTRAN code has been modernized by implementing a new mechanical model for the fuel rod cladding stress-strain analysis. FRAPTRAN-GENFLO and the new mechanical modelling have been successfully validated against the OECD Halden Project LOCA experiments.
Original languageEnglish
Title of host publicationSAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006
Subtitle of host publicationFinal Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages69-78
ISBN (Electronic)951-38-6887-7
ISBN (Print)951-38-6886-9
Publication statusPublished - 2006
MoE publication typeNot Eligible

Publication series

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2363
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

Fingerprint

Loss of coolant accidents
Hydraulic models
Nuclear fuels
Experiments
Hot Temperature

Cite this

Knuutila, A., Miettinen, J., & Stengård, J-O. (2006). Improvements in transient fuel performance modelling. In SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report (pp. 69-78). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2363
Knuutila, Arttu ; Miettinen, Jaakko ; Stengård, Jan-Olof. / Improvements in transient fuel performance modelling. SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. Espoo : VTT Technical Research Centre of Finland, 2006. pp. 69-78 (VTT Tiedotteita - Research Notes; No. 2363).
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Knuutila, A, Miettinen, J & Stengård, J-O 2006, Improvements in transient fuel performance modelling. in SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2363, pp. 69-78.

Improvements in transient fuel performance modelling. / Knuutila, Arttu; Miettinen, Jaakko; Stengård, Jan-Olof.

SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. Espoo : VTT Technical Research Centre of Finland, 2006. p. 69-78 (VTT Tiedotteita - Research Notes; No. 2363).

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

TY - CHAP

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AU - Stengård, Jan-Olof

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N2 - VTT employs the fuel transient performance code FRAPTRAN for safety-related analyses of nuclear fuel. Within the High-burnup Upgrades in Fuel Behaviour Modelling research task (KORU), capabilities of FRAPTRAN have been improved by coupling the fuel performance code to an advanced thermal hydraulic model GENFLO. Further, the mechanical modelling in the FRAPTRAN code has been modernized by implementing a new mechanical model for the fuel rod cladding stress-strain analysis. FRAPTRAN-GENFLO and the new mechanical modelling have been successfully validated against the OECD Halden Project LOCA experiments.

AB - VTT employs the fuel transient performance code FRAPTRAN for safety-related analyses of nuclear fuel. Within the High-burnup Upgrades in Fuel Behaviour Modelling research task (KORU), capabilities of FRAPTRAN have been improved by coupling the fuel performance code to an advanced thermal hydraulic model GENFLO. Further, the mechanical modelling in the FRAPTRAN code has been modernized by implementing a new mechanical model for the fuel rod cladding stress-strain analysis. FRAPTRAN-GENFLO and the new mechanical modelling have been successfully validated against the OECD Halden Project LOCA experiments.

M3 - Chapter or book article

SN - 951-38-6886-9

T3 - VTT Tiedotteita - Research Notes

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BT - SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006

PB - VTT Technical Research Centre of Finland

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Knuutila A, Miettinen J, Stengård J-O. Improvements in transient fuel performance modelling. In SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. Espoo: VTT Technical Research Centre of Finland. 2006. p. 69-78. (VTT Tiedotteita - Research Notes; No. 2363).