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NEA-1773 IFPE/IFA-591.

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

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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 specified machine
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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 specified programming language
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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.