Report on an experimental campaign on cladding transient behaviour

Rami Pohja; Santtu Huotilainen

Report on an experimental campaign on cladding transient behaviour

Rami Pohja, Santtu Huotilainen

VTT Technical Research Centre of Finland

Research output: Book/Report › Report

Abstract

The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial reactors. The fuel cladding creep test data including temperature and/or load drops is valuable for building the understanding of recovery phenomena in zirconium alloys during creep, but also scarce in open literature. The actions related to the preparation for the transient creep tests for Zirconium-based fuel cladding materials are briefly described in this report.

Original language	English
Publisher	VTT Technical Research Centre of Finland
Publication status	Published - 2017
MoE publication type	D4 Published development or research report or study

Publication series

Series	VTT Research Report
Volume	VTT-R-00799-17

Keywords

cladding creep
experimental research

PANCHO - Physics and Chemistry of Nuclear Fuel
Tulkki, V., Loukusa, H., Heikinheimo, J., Peltonen, J., Arkoma, A., Myllykylä, E. & Pohja, R.
1/01/15 → 31/01/18
Project: Other

Cite this

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title = "Report on an experimental campaign on cladding transient behaviour",

abstract = "The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial reactors. The fuel cladding creep test data including temperature and/or load drops is valuable for building the understanding of recovery phenomena in zirconium alloys during creep, but also scarce in open literature. The actions related to the preparation for the transient creep tests for Zirconium-based fuel cladding materials are briefly described in this report.",

keywords = "cladding creep, experimental research",

author = "Rami Pohja and Santtu Huotilainen",

note = "Project code: 113436 ",

year = "2017",

language = "English",

series = "VTT Research Report",

publisher = "VTT Technical Research Centre of Finland",

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TY - BOOK

T1 - Report on an experimental campaign on cladding transient behaviour

AU - Pohja, Rami

AU - Huotilainen, Santtu

N1 - Project code: 113436

PY - 2017

Y1 - 2017

N2 - The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial reactors. The fuel cladding creep test data including temperature and/or load drops is valuable for building the understanding of recovery phenomena in zirconium alloys during creep, but also scarce in open literature. The actions related to the preparation for the transient creep tests for Zirconium-based fuel cladding materials are briefly described in this report.

AB - The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial reactors. The fuel cladding creep test data including temperature and/or load drops is valuable for building the understanding of recovery phenomena in zirconium alloys during creep, but also scarce in open literature. The actions related to the preparation for the transient creep tests for Zirconium-based fuel cladding materials are briefly described in this report.

Report on an experimental campaign on cladding transient behaviour

Abstract

Publication series

Keywords

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Projects

PANCHO - Physics and Chemistry of Nuclear Fuel

Cite this