Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1547 IFPE/IFA-562.1.
last modified: 12-NOV-1997 | catalog | new | search |

NEA-1547 IFPE/IFA-562.1.

IFPE/IFA-562.1, Pellet Surface Roughness Effect on Thermal Performances and PCMI

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1. NAME OF EXPERIMENT

IFPE/IFA-562.1

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2. COMPUTERS

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Program name Package id Status Status date
IFPE/IFA-562.1 NEA-1547/01 Arrived 12-NOV-1997

Machines used:

Package ID Orig. computer Test computer
NEA-1547/01 Many Computers
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3. DESCRIPTION

Twelve fuel rods assembled in two axially separated clusters were irradiated in the Halden Boiling Water Reactor as IFA-562.1 from June 1987 to August 1989 in order to investigate the effect of pellet surface roughness on both fuel thermal and rod mechanical performances. As a second experimental objective the fuel grain growth caused by a power ramp at the end of the irradiation period was intended to investigate by PIE. To achieve the objectives fuel centre temperatures and clad elongation were measured in the fuel roads containing either rough or smooth pellets and filled with xenon or helium gas. To provide ideal conditions for the comparison of smooth and rough pellet rods' behaviour, the rods were fabricated with small fuel-clad gap size and the fuel temperatures were kept below 1200 C-degree during the base irradiation. The small initial gap size provided gap closure, and the low fuel centre temperature prevented both fission gas release and grain growth. Nevertheless, no systematic differences have been observed in either thermal or mechanical behaviour of the smooth and rough pellet rods. Consequently the effect of pellet surface roughness is insignificant in comparison with other influences as the pellet-cladding gap size change, fuel densification and relocation. During the final high power period the fuel temperature increase induced measurable grain growth in a few sample from the upper cluster.

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9. STATUS
Package ID Status date Status
NEA-1547/01 12-NOV-1997 Masterfiled restricted
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10. REFERENCES
NEA-1547/01, included references:
- P.M. Crosby and C. Vitanza: Irradiation of the Pellet Roughness Rig IFA-562
Progress Report March 1988, HWR-238
- M.R. Smith: Final Report on the In-Pile Results from the Pellet Roughness
Test in Rig IFA-562, HWR-245 (November 1989)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. AUTHORS

OECD Halden Reactor Project

Institutt for Energiteknikk

P.O. Box 173

N-1751 HALDEN

Norway

 

Compilation: Cs. Gyori

 

Review: J.A. Turnbull

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16. MATERIAL AVAILABLE
NEA-1547/01
EC\            Measured cladding elongation during slow power reductions at
five different burnup levels
HISTORY\       Condensed history files for each fuel rod
TEMP\BURNUP\   Contains the fuel centre temperatures as the function of local
burnup at a constant 25 Kw/m local heat rate
TEMP\POWER\    Fuel centre temperature data as the function of power at the
five different burnup levels
RAMP\          Data for each rod during the final high power period
PLOT\          Postscript format of the figures being referred in the files
READ.ME        Information file
562-1.sum      Summary about the experiment
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: BWR reactors, burnup, experimental data, fission products, fuel elements, fuel pellets, fuel rods, fuel-cladding interaction, thermal conductivity.