Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects

NEA-1645 IFPE/EFE-RO

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

NEA-1645 IFPE/EFE-RO

IFPE/EFE-RO, Experimental Fuel Elements RO89 and RO51 in TRIGA 14 MW Reactor (INR-Pitesti)

NAME, COMPUTER, PROBLEM, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME

IFPE/EFE-RO

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2. COMPUTERS

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Program name	Package id	Status	Status date
IFPE/EFE-RO	NEA-1645/03	Arrived	16-JAN-2023

Machines used:

Package ID	Orig. computer	Test computer
NEA-1645/03	Many Computers

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3. DESCRIPTION

Romanian irradiation tests concerned with CANDU type fuel elements behavior and with the limits of the design parameters. A particular feature of the CANDU fuel project is the small plenum (void volume) added for relaxation of the fission gases, which are inherently released during the fuel irradiation. Two irradiation tests in the C2 device from the TRIGA 14MW reactor were performed between the years 1985-1987. The tests were done to evaluate the effect of the fuel density on the time-evolution of the fission gas pressure. Experimental fuel elements were adequately instrumented with pressure transducers to follow the fission gas pressure changes during fuel irradiation. The first irradiation test was conducted on the fuel element coded No.89 whose main characteristics were the nominal values of the main fuel design parameters. The second one was conducted on the fuel element coded No.51. Because of the axial flux asymmetry inside the TRIGA reactor core, the experimental elements are shorter in length than the CANDU fuel design.

The irradiation tests consisted in evaluation of the time-evolution of the internal pressure from two experimental fuel elements having the main design characteristics as the Romanian CANDU type fuel element design and to follow the dependence of the internal pressure of the fission gas on the fuel density.

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9. STATUS

Package ID	Status date	Status
NEA-1645/03	16-JAN-2023	Masterfiled restricted

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10. REFERENCES

NEA-1645/03, included references:

- Raport de Iradiere a Elementului Combustibil NR.51 Iradiat in Capsula C2,
Campania A 7-a, Internal Report 78-RI 2375 (20.12.1987) in Romanian
- Raport Privind Efectul Densitatii Pastilelor Asupra Evolutiei Presiunii
Gazelor de Fisiune in Timpul Iradierii Elementului Combustibil Nr.51, Interal
Report Nr.2573/1988 (in Romanian)
- M. C. Paraschiv: The Romanian Irradiation Tests Prepared For IAEA/OECD
Database
- Raport de Iradiere a Elementului Combustibil NR.89 Iradiat in Capsula C2,
Campania a V-a, Internal Report 78-RI 1993 (20.06.1986) (in Romanian)
- Raport Privind Efectul Densitatii Pastilelor de UO2 Asupra Evolutiei
Presiunii Gazelor de Fisiune in Timpul Iradierii, Interal Report Nr.2130
(20.12.1986) (in Romanian)

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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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15. AUTHORS

Marius PARASCHIV

Institute for Nuclear Research

P.O. Box 78

03000 Pitesti

ROMANIA

Review: J.A. Turnbull

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16. MATERIAL AVAILABLE

NEA-1645/03

EC-No51.dat    Irradiation parameters and power history of fuel element No.51
Ist51-1.dat    Data used to build Fig.3.3
Ist51-2.dat    Internal pressure history on the fuel element No.51 taken from
Table 4
Ist51-3.dat    Power history and internal pressure history during the 4
sensitive tests
Ist51-12.dat   Data used to build Fig.4.10
EC-No89.dat    Irradiation parameters and power history of fuel element No.89
Ist89-1.dat    Data used to build Fig.3.1
Ist89-2.dat    Internal pressure history on the fuel element No.89 taken from
Table 5
Ist89-3.dat    Power history and internal pressure history during the 4
sensitive tests
Ist89-12.dat   Data used to build Fig.4.8
QA_File        QA report
Read_me        Readme file
Summary_oecd.pdf   Summary of the irradiation tests on the fuel elements No.89
and No.51

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

Keywords: database, experimental data, fuel elements, irradiation.