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NEA-1803 IFPE/IFA-585.

IFPE/IFA-585, In-Reactor Creep Behaviour of Zircaloy-2 and Zircaloy-4 under Variable Loading Conditions

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1. NAME OF EXPERIMENT:  IFPE/IFA-585.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/IFA-585 NEA-1803/01 Arrived 13-MAR-2008

Machines used:

Package ID Orig. computer Test computer
NEA-1803/01 Many Computers
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3. DESCRIPTION

The test assembly IFA-585 was designed to study in-reactor creep behaviour of Zircaloy cladding under variable stress conditions. The first loading of the assembly contained two short rods, one fabricated from pre-irradiated Zr-2 (the BWR rod) and the other from unirradiated Zr-4 (the PWR rod). The diameter gauge on the PWR rod ceased functioning after about 8500 hours, but that on the BWR rod continued to give results until the end of the first loading in October 1995.
  
Diameter change measurements were collected regularly from the BWR rod over its 14,400 hours dwell in reactor. During this time the fast neutron flux averaged 3.2 10e+13 n/cm**2/s whilst the cladding temperature stayed between 300 and 320 'C. The applied hoop stress was changed nine times within the range -160 to +130 MPa, from compression to tension and vice versa.
  
From the measured variation in rod diameter with time at power, the following parameters have been determined for each stress level: elastic loading strain, primary creep strain and secondary creep rate. Although sometimes difficult to detect, primary creep is exhibited after each stress change resulting in a new secondary creep rate. Total primary strain has been shown to be proportional to the preceding change in stress and to exhibit no asymmetry between tension and compression. The stress dependence of the secondary creep rate is nearly linear and it is observed that the creep rate in tension is generally higher than that in compression for a given stress.
The loading strain conforms to elastic behaviour and has been removed from the total diameter change measurements in order to obtain inelastic (creep) strain allowing comparison of the experimental results to existing creep models. Comparison is made to two creep models for Zircaloy, one based on in-reactor results, the other thermal creep results. In both cases the agreement is quite good.
Operating conditions:
  
PARAMETER                     Upper Zr-4 Tube Lower          Zr-2 Tube
Peak power                    400 W/cm, peak power at        Zero
                              lower end, max-to-min
                              power ratio = 1.15
Cladding temperature at O.D.  350 deg.C                      305 deg.C
Coolant temperature           305 deg.C inlet
                              325 deg.C outlet

Coolant flow velocity         1.8 m/s
Coolant Pressure              162 bar
Fast Flux                     5.10e+13 n/cm**2s (>1 MeV)
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9. STATUS
Package ID Status date Status
NEA-1803/01 13-MAR-2008 Arrived restricted
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10. REFERENCES
NEA-1803/01, included references:
- A.T. Donaldson
In-Reactor Creep Behaviour of Zircaloy under Variable Loading Conditions in
IFA-585, HWR-413, October 1994
- M. McGrath
In-Reactor Creep Behaviour of Zircaloy-2 under Variable Loading
Conditions in IFA-585, HWR-471, March 1996
- Comments on data in the Excel spreadsheets: A synopsis of discussions with M.
A. McGrath of Halden Project (2008)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Margaret MCGRATH and A.T. Donaldson
OECD Halden Reactor Project
Institutt for Energiteknikk
Os Alle 13 - P.O. Box 173
N-1751 HALDEN
Norway
  
Compilation: J.A. Turnbull, UK
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16. MATERIAL AVAILABLE
NEA-1803/01
- IFA-585-PWR-creepdata: data from the whole of the rod
- IFA-585-BWR-HALF-new-creepdata: data from the top half
- Zr-2 history
- excel_outfile-PWRU
- Comments on data in the Excel spreadsheets
- HWR-413.pdf and HWR-471.pdf: Electronic documentation
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: compression, hoop stress, in-reactor creep, nuclear fuels, rod diameter, tension, zircaloy cladding.