Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects

NEA-1773 IFPE/IFA-591.

last modified: 16-JAN-2023 | catalog | new | search |

NEA-1773 IFPE/IFA-591.

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

NAME, COMPUTER, PROBLEM, STATUS, REFERENCES, LANGUAGE, AUTHOR, 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-1773/03	Arrived	16-JAN-2023

Machines used:

Package ID	Orig. computer	Test computer
NEA-1773/03	Many Computers

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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-1773/03	16-JAN-2023	Masterfiled restricted

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10. REFERENCES

NEA-1773/03, 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. AUTHORS

JAEA

4-33 Muramatsu, Tokai-mura

Naka-gun

Ibaraki-ken

JAPAN

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16. MATERIAL AVAILABLE

NEA-1773/03

591-*.xls                      Ramp test history and in-pile data
Base iradiated segments.txt
E07 inner segment re2.xls
E07 intermediate segment re2.xls
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
IFA591 data for IFPE r1.txt    List of files
READ ME_PIE data.txt           List of PIE data files
READ ME_Ramp test history and in-pile data.txt
Summary.doc                    Description of the irradiation and results

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

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