KOTO special report

Effect of creep on fuel behaviour in RIA

Arttu Knuutila

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

Abstract

Creep is a high temperature deformation mechanism that becomes significant when the temperature exceeds about half of the material absolute melting point. An earlier study at VTT shows that creep is a significant deformation mechanism in certain reactivity initiated accidents (RIA). So, to be able to realistically simulate RIA creep has to be included in the simulation. VTT Energy is using the SCANAIR computer code to analyse the behaviour of nuclear fuel in accident conditions. The code is meant to simulate a reactivity-initiated accident in a light water reactor. SCANAIR was designed to handle the closely interconnected thermal-mechanical calculations that are needed to simulate the accident behaviour of a fuel rod. The code simulates the thermal-mechanical behaviour of a single nuclear fuel rod with numerical models. A finite element model is used in the mechanical module of SCANAIR to simulate the mechanical behaviour of the rod. The mechanical module is designed to describe the highly nonlinear mechanical behaviour of the fuel rod taking into account elasticity, plasticity, thermal expansion, cracking, and fission gas swelling. Also a creep model has been implemented in SCANAIR module at VTT Energy. This paper briefly describes the implemented creep model in the SCANAIR code. A simple example calculation is also made with SCANAIR to show the effect of the creep on RIA calculation.
Original languageEnglish
Title of host publicationFINNUS: The Finnish Research Programme on Nuclear Power Plant Safety
Subtitle of host publicationInterim Report 1999 - August 2000
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages142-150
ISBN (Electronic)951-38-5751-4
ISBN (Print)951-38-5750-7
Publication statusPublished - 2000
MoE publication typeD2 Article in professional manuals or guides or professional information systems or text book material

Publication series

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2057
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

Fingerprint

Accidents
Creep
Nuclear fuels
Light water reactors
Thermal expansion
Plasticity
Swelling
Melting point
Numerical models
Elasticity
Temperature
Gases
Hot Temperature

Cite this

Knuutila, A. (2000). KOTO special report: Effect of creep on fuel behaviour in RIA. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety: Interim Report 1999 - August 2000 (pp. 142-150). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2057
Knuutila, Arttu. / KOTO special report : Effect of creep on fuel behaviour in RIA. FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety: Interim Report 1999 - August 2000. Espoo : VTT Technical Research Centre of Finland, 2000. pp. 142-150 (VTT Tiedotteita - Research Notes; No. 2057).
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Knuutila, A 2000, KOTO special report: Effect of creep on fuel behaviour in RIA. in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety: Interim Report 1999 - August 2000. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2057, pp. 142-150.

KOTO special report : Effect of creep on fuel behaviour in RIA. / Knuutila, Arttu.

FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety: Interim Report 1999 - August 2000. Espoo : VTT Technical Research Centre of Finland, 2000. p. 142-150 (VTT Tiedotteita - Research Notes; No. 2057).

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

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M3 - Chapter or book article

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Knuutila A. KOTO special report: Effect of creep on fuel behaviour in RIA. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety: Interim Report 1999 - August 2000. Espoo: VTT Technical Research Centre of Finland. 2000. p. 142-150. (VTT Tiedotteita - Research Notes; No. 2057).