Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1803 IFPE/IFA-585.
last modified: 13-MAR-2008 | catalog | new | search |

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

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

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.

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9. STATUS
Package ID Status date Status
NEA-1803/01 13-MAR-2008 Masterfiled 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. AUTHORS

Margaret MCGRATH and A.T. Donaldson

OECD Halden Reactor Project

Institutt for Energiteknikk

P.O. Box 173

N-1751 HALDEN

Norway

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16. MATERIAL AVAILABLE
NEA-1803/01
IFA-585-PWR-creepdata.xls            Data from the whole of the rod
IFA-585-BWR-HALF-new-creepdata.xls   Data from the top half
excel_outfile-PWRU.xls
Zr-2 history.xls
Comments on data in the Excel spreadsheets.doc
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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.