NEA-1645 IFPE/EFE-RO
IFPE/EFE-RO, Experimental Fuel Elements RO89 and RO51 in TRIGA 14 MW Reactor (INR-Pitesti)
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, STATUS, REFERENCES, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/EFE-RO51 | NEA-1645/01 | Arrived | 02-APR-2002 |
| IFPE/EFE-RO89 | NEA-1645/02 | Arrived | 02-APR-2002 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1645/01 | Many Computers | |
| NEA-1645/02 | Many Computers |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
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.
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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| Package ID | Status date | Status |
|---|---|---|
| NEA-1645/01 | 02-APR-2002 | Arrived at NEADB |
| NEA-1645/02 | 02-APR-2002 | Arrived at NEADB |
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NEA-1645/01, included references:
- Raport de Iradiere a Elementului Combustibil NR.51 Iradiat inCapsula C2, Campania A 7-a
Internal Report 78-RI 2375 (20.12.1987) in Rumanian
- Raport Privind Efectul Densitatii Pastilelor Asupra Evolutiei
Presiunii Gazelor de Fisiune in Timpul Iradierii Elementului Combustibil Nr.51
Interal Report Nr.2573/1988 (in Rumanian)
- M. C. Paraschiv:
The Romanian Irradiation Tests Prepared For IAEA/OECD Database
NEA-1645/02, included references:
- Raport de Iradiere a Elementului Combustibil NR.89 Iradiat inCapsula C2, Campania a V-a
Internal Report 78-RI 1993 (20.06.1986) in Rumanian
- Raport Privind Efectul Densitatii Pastilelor de UO2 Asupra Evolutiei
Presiunii Gazelor de Fisiune in Timpul Iradierii
Interal Report Nr.2130 (20.12.1986) (in Rumanian)
- M. C. Paraschiv:
The Romanian Irradiation Tests Prepared For IAEA/OECD Database
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NEA-1645/01
EC-No51.dat Irradiation parameters and power historyIst51-1 - the data used to build Fig.3.3
Ist51-12 - the data used to build Fig.4.10
Ist51-2 - Internal pressure history on the fuel elem. No.51 taken from Table 4
Ist51-3 power hist. and internal pressure hist. during the 4 sensitive tests
QA_File All observations
Read_me Information about the data files
RI2375 Internal report
RI2573 Internal report
Summary_oecd Summary of the tests on the fuel elements No.89 and No.51
letter.pdf letter from M. Paraschiv
The Romanian Irradiation Tests Prepared For IAEA/OECD Database
NEA-1645/02
EC-No89.dat Irradiation parameters and power historyIst89-1 - the data used to build Fig.3.1
Ist89-12 - the data used to build Fig.4.8
Ist89-2 - Internal pressure history on the fuel elem. No.51 taken from Table 5
Ist89-3 power hist. and internal pressure hist. during the 4 sensitive tests
QA_File All observations
Read_me Information about the data files
RI1993 Internal report
RI2130 Internal report
Summary_oecd Summary of the tests on the fuel elements No.89 and No.51
letter.pdf letter from M. Paraschiv
The Romanian Irradiation Tests Prepared For IAEA/OECD Database
Keywords: data base systems, fuel elements, irradiation.