Multiaxial creep testing device for nuclear fuel claddings

Rami Pohja, Pekka Moilanen, Juhani Rantala, Santtu Huotilainen, Ville Tulkki, Ulla Ehrnstén, Stefan Holmström

Research output: Contribution to journalArticleScientificpeer-review

Abstract

Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.
Original languageEnglish
Pages (from-to)227-240
JournalAthens Journal of Sciences
Volume3
Issue number3
Publication statusPublished - 2016
MoE publication typeA1 Journal article-refereed

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Nuclear fuel cladding
Creep testing
Creep
Pneumatics
Nuclear reactors
Accidents
Testing
Zirconium alloys
Creep resistance
Austenitic stainless steel
Mechanical properties

Keywords

  • fuel cladding
  • mechanical testing
  • multiaxial creep
  • nuclear reactor
  • pneumatic loading apparatus

Cite this

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title = "Multiaxial creep testing device for nuclear fuel claddings",
abstract = "Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.",
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note = "SDA: SHP: SASUNE Nuclear",
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language = "English",
volume = "3",
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journal = "Athens Journal of Sciences",
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Multiaxial creep testing device for nuclear fuel claddings. / Pohja, Rami; Moilanen, Pekka; Rantala, Juhani; Huotilainen, Santtu; Tulkki, Ville; Ehrnstén, Ulla; Holmström, Stefan.

In: Athens Journal of Sciences, Vol. 3, No. 3, 2016, p. 227-240.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Multiaxial creep testing device for nuclear fuel claddings

AU - Pohja, Rami

AU - Moilanen, Pekka

AU - Rantala, Juhani

AU - Huotilainen, Santtu

AU - Tulkki, Ville

AU - Ehrnstén, Ulla

AU - Holmström, Stefan

N1 - SDA: SHP: SASUNE Nuclear

PY - 2016

Y1 - 2016

N2 - Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.

AB - Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.

KW - fuel cladding

KW - mechanical testing

KW - multiaxial creep

KW - nuclear reactor

KW - pneumatic loading apparatus

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JO - Athens Journal of Sciences

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