NEA-1861 IFPE/IFA-629.1.
IFPE/IFA-629.1, The Re-irradiation of MIMAS-MOX Fuel in IFA-629.1
NAME OF EXPERIMENT, COMPUTER, DESCRIPTION OF EXPERIMENT, STATUS, REFERENCES, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/IFA-629.1 | NEA-1861/01 | Arrived | 12-OCT-2011 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1861/01 | Many Computers |
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3. DESCRIPTION OF EXPERIMENT
Two segments from MOX-rod J09 which had been irradiated for two cycles in the Saint Laurent B1 reactor in France to approximately 25MWd/kgMOX were re-instrumented and re-irradiated in the Halden rig IFA-629.1. IFA-629.1 was irradiated under HBWR conditions (34 bar coolant pressure and 230~240?C) during June 1998 to May 1999[1]. Both rods were equipped with fuel thermocouples (TF) at the top end. At the lower end one rod (Rod 2) was equipped with a bellows pressure tranducer (PF) and the other (Rod 1) with a clad extensometer (EC).
The MOX pellets were manufactured by the MIMAS (Micronized Mater Blend) process. The fissile content of rod J09 is 4.134 wt %. Re-sintering tests show stable pellets, with a thermal densification of less than 1%. The Pu agglomerate size was 6.95 microns. The grain size of UO2 matrix averaged through a pellet was 11.7 microns.
After irradiation in IFA-629.1 in the HBWR, PIE was performed on Rod 2 at Kjeller to obtain information on fission gas release and swelling behaviour.
Two segments from MOX-rod J09 which had been irradiated for two cycles in the Saint Laurent B1 reactor in France to approximately 25MWd/kgMOX were re-instrumented and re-irradiated in the Halden rig IFA-629.1. IFA-629.1 was irradiated under HBWR conditions (34 bar coolant pressure and 230~240?C) during June 1998 to May 1999[1]. Both rods were equipped with fuel thermocouples (TF) at the top end. At the lower end one rod (Rod 2) was equipped with a bellows pressure tranducer (PF) and the other (Rod 1) with a clad extensometer (EC).
The MOX pellets were manufactured by the MIMAS (Micronized Mater Blend) process. The fissile content of rod J09 is 4.134 wt %. Re-sintering tests show stable pellets, with a thermal densification of less than 1%. The Pu agglomerate size was 6.95 microns. The grain size of UO2 matrix averaged through a pellet was 11.7 microns.
After irradiation in IFA-629.1 in the HBWR, PIE was performed on Rod 2 at Kjeller to obtain information on fission gas release and swelling behaviour.
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10. REFERENCES
- K. Lassmann, J. van de Laar:
A new Data-Condensation Method based on Multidimensional Minimisation, Technical Report JRC-ITU-TN-2001/32, 2001
- K. LASSMANN and J. van de LAAR:
"A new Data-Condensation Method Based on Multidimensional Minimisation", KERNTECHNIK 69 (2004) 21-25
- K. Lassmann, J. van de Laar:
A new Data-Condensation Method based on Multidimensional Minimisation, Technical Report JRC-ITU-TN-2001/32, 2001
- K. LASSMANN and J. van de LAAR:
"A new Data-Condensation Method Based on Multidimensional Minimisation", KERNTECHNIK 69 (2004) 21-25
NEA-1861/01, included references:
- Rodney J.White:?The Re-irradiation of MIMAS-MOX Fuel in IFA 629.1? (Documentation, HWR-586,
March 1999).
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NEA-1861/01
PRE-CHAR.TXT Pre characterization data BASE-HIST-R1.DAT Base irradiation histories in Saint Laurent B1, rod 1
BASE-HIST-R2.DAT Base irradiation histories in Saint Laurent B1, rod 2
629-R1.DAT Condensed HBWR irradiation histories for the re-instrumented rod 1 in
3 axial zones, bottom, middle, top, elevation of TF and average rod conditions.
629-R2.DAT Condensed HBWR irradiation histories for the re-instrumented rod 2 in
3 axial zones, bottom, middle, top, elevation of TF and average rod conditions.
TF1-LHRTF1.DAT Temperature vs. power for rod 1 during first ramps IFA-629.1
TF1-LHRTF2.DAT Temperature vs. power for rod 2 during first ramps IFA-629.1
629-1-TFDB.dat Full (uncondensed) irradiation history of IFA-629.1
629.1-TFDB-varlist.txt Description file of the variables included in the data
file 629-1-TFDB.dat
PIE-629-1.TXT File containing PIE data after Halden irradiation
README-629-1.TXT Readme
QAREP629.pdf QA report
HWR-586.pdf Electronic report
Summary629-1.pdf Description of the irradiation
Keywords: MOX, experimental data, fission gas release, fuels, pellet clad interaction (pci), thermal.