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NEA-1788 IFPE/BN-MOX-M109/D3.

IFPE/BN-MOX-M109/D3, Belgonucleaire Beznau-1 PWR irradiated MOX Fuel Rod M109/D3

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1. NAME OR DESIGNATION:  IFPE/BN-MOX-M109/D3
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/BN-MOX-M109/D3 NEA-1788/01 Arrived 30-MAY-2008

Machines used:

Package ID Orig. computer Test computer
NEA-1788/01 Many Computers
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3. DESCRIPTION

The aim of the NOK M109 International Programme was to investigate MOX fuel performance at high burnup.
Eight fuel rods, fabricated by BELGONUCLAIRE, were irradiated during five cycles in the Swiss BEZNAU-1 Pressurized Water Reactor to reach a peak burnup of about 47 GWd/tM. Post-irradiation examinations were performed on the eight fuel rods at the Paul Scherrer Institute laboratory.
  
The main fuel rod fabrication parameters, the irradiation characteristics and the post-irradiation results of the MOX fuel rod, irradiated in position D3 of the full MOX assembly M-109 are summarised hereafter. This fuel rod has reached a peak pellet burnup of 46.6 GWd/Tm.
  
Fuel Rod Fabrication:
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The fuel rod was manufactured by BELGONUCLEAIRE on the basis of the Westinghouse 14x14 fuel assembly design.
  
The cladding used for the rod fabrication is seamless Zircaloy 4 tube manufactured by Westinghouse Electric Corporation SMP (USA) from ingots provided by Western Zirconium Ogden, UT (USA).
  
The Zircaloy 4 cladding tubes were delivered to BELGONUCLEAIRE in one lot identified as BNT 104. All the tubes are annealed at 675 deg.C / 3 hours under vacuum before the final cold working and stress relieving.
  
The mixed oxide fuel pellets were manufactured by BELGONUCLEAIRE in its Dessel plant, using the MIMAS process (Micronized MASter blend process). Mixed oxide powder containing approximately 24 w/o plutonium was micronized and subsequently blended as master blend to free-flowing UO2 powder (AUC). The pellets were sintered at 1700 deg.C / 9 hours under argon + 5 v/o hydrogen.
  
The mixed oxide is composed of depleted uranium dioxide mixed with 4.24 % fissile plutonium. The O/M ratio was measured and yielded 1.995.
  
Irradiation History:
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The M-109 assembly was irradiated for 5 consecutive cycles (cycle 18 up to cycle 22) in the BEZNAU-1 reactor.
  
Post-Irradiation Examinations:
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Post-irradiation examinations performed on the D3 fuel rod at PSI include visual inspection of the rod, eddy current oxide thickness measurements, profilometry and length measurements, gamma scanning, gas puncture measurements, ceramographies and density measurements.
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9. STATUS
Package ID Status date Status
NEA-1788/01 30-MAY-2008 Arrived restricted
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10. REFERENCES
NEA-1788/01, included references:
- M. Lippens and Ch. Potten:
NOK M109, Data on the D3 MOX Fuel Rod (26 February 2007)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

M. Lippens and Ch. Potten
Belgonucleaire
Avenue Ariane, 4
B-1200, Brussels
Belgium
  
Revised by:
Mr. Larry J. OTT
Oak Ridge National Laboratory
MS-6167, P.O. Box 2008
Oak Ridge, TN 37831-6167
U.S.A.
  
Compiled by: J. A. TURNBULL
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16. MATERIAL AVAILABLE
NEA-1788/01
D3-REV.HIS : ASCII file of the irradiation in Beznau
QA report fo Beznau irradiated Rod D3.doc : details of how data were received
and processed
D3.IN : input file for Fortran processing program; included for QA purposes
only
D3LHR.xls : Linear Heat Rate
BEZNAU.FOR : FORTRAN processing program included for QA purposes only
alhgr_BEZNAU_2.for : Larry Ott's FORTRAN program
BEZNAU_8.out : Larry Ott's output file
Beznau_M109_D3_Ott-Transuranus-Frapcon3.xls' : TRANSURANUS Simulation,
FRAPCON-3 V. 2.0 Calculations, and Experimental Data (provided by Larry Ott)
BEZNAU D3.pdf : Report NOK M109, 'Data on the D3 MOX Fuel Rod'
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: MOX, database, pressurized water reactor.