Creep performance of fuel cladding

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

Abstract

The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.
Original languageEnglish
Title of host publicationBaltica X
Subtitle of host publicationInternational Conference on Life Management and Maintenance for Power Plants
EditorsPertti Auerkari
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Number of pages8
ISBN (Electronic)978-951-38-8436-9, 978-951-38-8435-2
Publication statusPublished - 2016
MoE publication typeA4 Article in a conference publication
EventBALTICA X - International Conference on Life Management and Maintenance for Power Plants - Cruise, Helsinki-Stockholm, Finland
Duration: 7 Jun 20169 Jun 2016

Publication series

NameVTT Technology
PublisherVTT
Volume261
ISSN (Electronic)2242-122X

Conference

ConferenceBALTICA X - International Conference on Life Management and Maintenance for Power Plants
Abbreviated titleBaltica X
CountryFinland
CityHelsinki-Stockholm
Period7/06/169/06/16

Fingerprint

Creep
Zirconium alloys
Nuclear fuel cladding
Nuclear reactors
Austenitic stainless steel
Pneumatics
Logistics
Testing
Temperature

Cite this

Pohja, R., Tulkki, V., Ikonen, T., Moilanen, P., Rantala, J., Huotilainen, S., & Ehrnstén, U. (2016). Creep performance of fuel cladding. In P. Auerkari (Ed.), Baltica X: International Conference on Life Management and Maintenance for Power Plants Espoo: VTT Technical Research Centre of Finland. VTT Technology, Vol.. 261
Pohja, Rami ; Tulkki, Ville ; Ikonen, Timo ; Moilanen, Pekka ; Rantala, Juhani ; Huotilainen, Santtu ; Ehrnstén, Ulla. / Creep performance of fuel cladding. Baltica X: International Conference on Life Management and Maintenance for Power Plants. editor / Pertti Auerkari. Espoo : VTT Technical Research Centre of Finland, 2016. (VTT Technology, Vol. 261).
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abstract = "The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.",
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Pohja, R, Tulkki, V, Ikonen, T, Moilanen, P, Rantala, J, Huotilainen, S & Ehrnstén, U 2016, Creep performance of fuel cladding. in P Auerkari (ed.), Baltica X: International Conference on Life Management and Maintenance for Power Plants. VTT Technical Research Centre of Finland, Espoo, VTT Technology, vol. 261, BALTICA X - International Conference on Life Management and Maintenance for Power Plants, Helsinki-Stockholm, Finland, 7/06/16.

Creep performance of fuel cladding. / Pohja, Rami; Tulkki, Ville; Ikonen, Timo; Moilanen, Pekka; Rantala, Juhani; Huotilainen, Santtu; Ehrnstén, Ulla.

Baltica X: International Conference on Life Management and Maintenance for Power Plants. ed. / Pertti Auerkari. Espoo : VTT Technical Research Centre of Finland, 2016. (VTT Technology, Vol. 261).

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

TY - GEN

T1 - Creep performance of fuel cladding

AU - Pohja, Rami

AU - Tulkki, Ville

AU - Ikonen, Timo

AU - Moilanen, Pekka

AU - Rantala, Juhani

AU - Huotilainen, Santtu

AU - Ehrnstén, Ulla

PY - 2016

Y1 - 2016

N2 - The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.

AB - The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.

M3 - Conference article in proceedings

T3 - VTT Technology

BT - Baltica X

A2 - Auerkari, Pertti

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Pohja R, Tulkki V, Ikonen T, Moilanen P, Rantala J, Huotilainen S et al. Creep performance of fuel cladding. In Auerkari P, editor, Baltica X: International Conference on Life Management and Maintenance for Power Plants. Espoo: VTT Technical Research Centre of Finland. 2016. (VTT Technology, Vol. 261).