NEA-1758 IFPE/NFIR-1.
IFPE/NFIR-1, Clad creepdown, power history effect on fission product distribution (6 PWR rods 40-64 MWd/kg in BR-3)
NAME OF EXPERIMENT, COMPUTER, DESCRIPTION, STATUS, REFERENCES, LANGUAGE, NAME AND ESTABLISHMENT, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/NFIR-1 | NEA-1758/01 | Arrived | 21-MAR-2006 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1758/01 | Many Computers |
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3. DESCRIPTION
The NFIR-1programme was designed to investigate factors likely to affect the fission gas release behaviour of fuel rods operating under normal commercial conditions. The factors which were investigated were:
- the effect of fuel/rod design parameters, e.g., wet versus dry route pellet manufacture, fuel-clad gap size and rod pressurization
- the effect of power history i.e., IN/OUT fuel management strategy
- the effect of burn-up extension.
This was accomplished by an extensive PIE campain on 6 fuel rods irradiated to 40-64 MWd/kg under different prescribed conditions in the BR3 PWR . The examination involved non destructive mensuration and destructive examination using optical, SEM, TEM and EPMA techniques. The dataset is unique in demonstrating the effect of these variables on fuel performance.
The NFIR-1programme was designed to investigate factors likely to affect the fission gas release behaviour of fuel rods operating under normal commercial conditions. The factors which were investigated were:
- the effect of fuel/rod design parameters, e.g., wet versus dry route pellet manufacture, fuel-clad gap size and rod pressurization
- the effect of power history i.e., IN/OUT fuel management strategy
- the effect of burn-up extension.
This was accomplished by an extensive PIE campain on 6 fuel rods irradiated to 40-64 MWd/kg under different prescribed conditions in the BR3 PWR . The examination involved non destructive mensuration and destructive examination using optical, SEM, TEM and EPMA techniques. The dataset is unique in demonstrating the effect of these variables on fuel performance.
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NEA-1758/01, included references:
- Properties of UO2 Irradiated to High Burnups, EPRI NP-5191-LD, ProjectX101-5, Final Report April 1987
- S. K. Yagnik, A.J. Machiels, R.L. Yang:
Characterization of UO2 irradiated in the BR-3 reactor
Journal of Nuclear Materials 270 (1999) 65-73
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NEA-1758/01
Summary of NFIR-1.doc : WORD file summarizing the dataseQA report for compiling dataset (WORD file)
Precharacterization.doc : WORD file summarizing pre-characterization
Tables_prechar_NFIR.xls : Excel file with tables
PIE summary.doc : WORD file summarizing PIE
Tables_PIE_NFIR.xls : Excel file with tables
Primary reports on NFIR-1 in PDF format
Rod power histories and axial power profiles (Excel files for each rod)
Ax.HIS : irradiation histories for each A rod (x = 1 to 5)
B1.HIS : irradiation history for rod B1
Ax-Fx : (x = 1-5), digitized data for axial variation of diametral strain for
Figures 5-1 through to 5-5
B1-F6 : digitized data for axial variation of diametral strain for rod B1 and
Figure 5-6
A11-F49 through to A52-F60 : EPMA radial profiles for Xe and Cs across specified
sections from A rods digitized from figures 5-49 through to 5-60
B11-F61 : EPMA radial profiles for Xe and Cs across specified sections for
section B11 and figure 5-61
A11-F62 through to A52-F66 : EPMA radial profiles for Pu across sections from A
rods digitized from figures 5-62 through to 5-66
B11-F67 : EPMA radial profiles for Pu across sections for section B11 and figure
5-67
Keywords: clad creepdown, fission gas release, fission product distribution, pressurized water reactor.