NEA-1773 IFPE/IFA-591.

IFPE/IFA-591, JAEA Power Ramp Tests of MOX Fuel Rods IFA-591

NAME OF EXPERIMENT, COMPUTER, DESCRIPTION, STATUS, REFERENCES, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OF EXPERIMENT: IFPE/IFA-591

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2. COMPUTERS

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Program name	Package id	Status	Status date
IFPE/IFA-591	NEA-1773/01	Arrived	12-APR-2007

Machines used:

No item found

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3. DESCRIPTION

Plutonium-uranium mixed oxide (MOX) fuel rods of instrumental rig IFA-591 were ramped in HBWR to study the Advanced Thermal Reactor (ATR) MOX fuel behaviour during transient operation and to determine a failure threshold of the MOX fuel rods. Eleven segments were base-irradiated in ATR "FUGEN" up to 18.4 GWd/t. Zirconium liner claddings were adopted for four segments of them. As the results of non-destructive post irradiation examinations (PIEs) after the base-irradiation and before the ramp tests, no remarkable behaviour affecting the integrity of fuel assembly and fuel rod was confirmed.

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9. STATUS

Package ID	Status date	Status
NEA-1773/01	12-APR-2007	Arrived at NEADB

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10. REFERENCES

NEA-1773/01, included references:

- Takayuki OZAWA and Tomoyuki ABE:
Power Ramp Tests of MOX Fuel Rods - HBWR Irradiation with the Instrument Rig,
IFA-591
JAEA-Technology 2006-026 (March 2006)

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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

JAEA
4-33 Muramatsu, Tokai-mura
Naka-gun
Ibaraki-ken
JAPAN

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16. MATERIAL AVAILABLE

NEA-1773/01

SUMMARY.doc Description of the irradiation and results
Base irradiation history
E07 inner segment.xls
E07 intermediate segment.xls
Base iradiated segments.txt
Ramp test history and in-pile data
Ramp history files
PIE data
Profilometry after base irradiation.xls
Profilometry before ramp test.xls
Peak linear power.xls
Relaxation rate.xls
Inner pressure.xls
Fission gas release rate.xls
Retained fission gas.xls

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

Keywords: MOX, fuel behaviour, plutonium, power ramp, uranium.