last modified: 21-MAR-2006 | catalog | categories | new | search |

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)

top ]
1. NAME OF EXPERIMENT:  IFPE/NFIR-1.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
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
top ]
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.
top ]
9. STATUS
Package ID Status date Status
NEA-1758/01 21-MAR-2006 Arrived at NEADB
top ]
10. REFERENCES
NEA-1758/01, included references:
- Properties of UO2 Irradiated to High Burnups, EPRI NP-5191-LD, Project
X101-5, 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
top ]
12. PROGRAMMING LANGUAGE(S) USED

No item found

top ]
15. NAME AND ESTABLISHMENT

Files supplied by:
EPRI
3412 Hillview Avenue
Palo Alto, CA 94304
U.S.A.
  
Compilation: J.A. Turnbull
top ]
16. MATERIAL AVAILABLE
NEA-1758/01
Summary of NFIR-1.doc :  WORD file summarizing the datase
QA 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
top ]
17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: clad creepdown, fission gas release, fission product distribution, pressurized water reactor.