Thermal isocreep curves obtained during multi-axial creep tests on recrystallized Zircaloy-4 and M5™ alloy
- 1. CIRIMAT, CNRS/UPS/INPT, 4 allée Emile Monso, 31030 Toulouse (France)
- 2. AREVA, AREVA NP, 10 rue Juliette Récamier, 69456 Lyon (France)
- 3. LIMATB, University Bretagne-Sud, rue de Saint-Maudé, 56321 Lorient (France)
- 4. LEMMA, Université de La Rochelle, Avenue Michel Crépeau, 17042 La Rochelle (France)
Description
Zirconium alloys are widely used in the nuclear industry. Several components, such as cladding or guide tubes, undergo strong mechanical loading during and after their use inside the pressurized water reactors. The current requirements on higher fuel performances lead to the developing on new Zr based alloys exhibiting better mechanical properties. In this framework, creep behaviors of recrystallized Zircaloy-4 and M5™, have been investigated and then compared. In order to give a better understanding of the thermal creep anisotropy of Zr-based alloys, multi-axial creep tests have been carried out at 673 K. Using a specific device, creep conditions have been set using different values of β = σzz/σθθ, σzz and σθθ being respectively the axial and hoop creep stresses. Both axial and hoop strains are measured during each test which is carried out until stationary creep is stabilized. The steady-state strain rates are then used to build isocreep curves. Considering the isocreep curves, the M5™ alloy shows a largely improved creep resistance compared to the recrystallized Zircaloy-4, especially for tubes under high hoop loadings (0 < β < 1). The isocreep curves are then compared with simulations performed using two different mechanical models. Model 1 uses a von Mises yield criterion, the model 2 is based on a Hill yield criterion. For both models, a coefficient derived from Norton law is used to assess the stress dependence
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2013.08.002Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2013.08.002;
- PII
- S0029-5493(13)00351-8;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 269
- Journal Page Range
- p. 33-37
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- International conference on structural mechanics in reactor technology
- Acronym
- SMiRT21
- Dates
- 6-11 Nov 2011
- Place
- New Delhi (India)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46019495
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANISOTROPY; CLADDING; CREEP; DIAGRAMS; GUIDE TUBES; PERFORMANCE; PWR TYPE REACTORS; RECRYSTALLIZATION; SIMULATION; STEADY-STATE CONDITIONS; STRAIN RATE; STRESSES; ZIRCALOY 4; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-4; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INFORMATION; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; SURFACE COATING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.