Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1758 IFPE/NFIR-1.
last modified: 21-MAR-2006 | catalog | 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)

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1. NAME OF EXPERIMENT

IFPE/NFIR-1

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users 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
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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.

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9. STATUS
Package ID Status date Status
NEA-1758/01 21-MAR-2006 Masterfiled restricted
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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
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. AUTHORS

EPRI

3412 Hillview Avenue

Palo Alto, CA 94304

USA

 

Compilation: J.A. Turnbull

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16. MATERIAL AVAILABLE
NEA-1758/01
Ax.HIS ---Irradiation histories for each A rod (x = 1 to 5)
Ax-Fx ----(x = 1-5), digitized data for axial variation of diametral strain for
Figures 5-1 through to 5-5
B1.HIS---Irradiation history for rod B1
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
Rod power histories and axial power profiles
PIE: summary of measurements
Pre-characterization of NFIR -1 fuel rods
QA report
Readme file
Summary of the NFIR-1 Dataset
Tables_prechar_NFIR.xls
Tables_PIE_NFIR.xls
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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