last modified: 29-JAN-2007 | catalog | categories | new | search |

NEA-1774 IFPE/FMDP-MOX4-5.

IFPE/FMDP-MOX4-5, Weapons-Derived MOX Fuel DOE FMDP Test Irradiations Capsules 4 & 5, Advanced Test Reactor (ATR)

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1. NAME OR DESIGNATION:  IFPE/FMDP-MOX4-5.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/FMDP-MOX4-5 NEA-1774/01 Arrived 29-JAN-2007

Machines used:

Package ID Orig. computer Test computer
NEA-1774/01 Many Computers
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3. DESCRIPTION

Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a burnup of 50 GWd/MT. The MOX fuel was fabricated at Los Alamos National Laboratory by a master-mix process and has been irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). Previous withdrawals of the same fuel have occurred at 9, 21, 30, and 40 GWd/MT. Oak Ridge National Laboratory manages this test series for the Department of Energy's Fissile Materials Disposition Program (FMDP). Description is given of the preparation of the MOX fuel, the equipment design, and the irradiation history of the test capsules, and the significance of the more important observations of the post-irradiation examinations (PIEs) is discussed. Code predictions (Frapcon-3 and TRANSURANUS) are presented and compared with available PIE data for the highest and lowest powered MOX capsules. Fuel performance has been excellent and consistent with code predictions and with existing U.S.and European experience.
  
Pin 7 was irradiated in Capsule 4 and pin 8 was irradiated in capsule 5.
  
These data are restricted to the benchmark participants.
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9. STATUS
Package ID Status date Status
NEA-1774/01 29-JAN-2007 Arrived restricted
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10. REFERENCES
NEA-1774/01, included references:
- L. J. Ott:
Irradiation Tests of Mixed-Oxide Fuel Prepared with Weapons-Derived Plutonium
- L. J. Ott:
Weapons-Derived MOX Fuel Benchmark Based on the DOE FMDP Test Irradiations for
Capsules 4 and 5 (PROPOSAL) (30 January 2007)
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

Data supplied by:
Larry J. Ott
Nuclear Science and Technology Division
Oak Ridge National Laboratory
MS-6167, P.O. Box 2008
Oak Ridge, TN 37831-6167
USA
  
For the:
OECD/NEA Expert Group on Reactor-Based Plutonium Disposition (TFRPD)
  
Compilation: J.A. Turnbull
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16. MATERIAL AVAILABLE
NEA-1774/01
3A.9.Ott_Paper.pdf    Pdf file summarizing the experiment
FMDP_Benchmark_PROPOSAL_final  Summary of the experiment
Pre-characterization.doc  File summarizing details of fuel, cladding and fuel
pins
PIE.doc File summarizing the data measured during PIE
CAP4-AV.HIS & CAP5-AV.HIS  Single zone irradiation histories for pins 7 and 8
irradiated in capsules 4 and 5 respectively
CAP4-Z.HIS & CAP5-Z.HIS  As above but as 16 zone irradiation histories
FPMA_FP7.DAT  Data file giving diameter values along pin 7
FPMA_FP8.DAT  Data file giving diameter values along pin 8
QA report for compiling dataset
Readme file
WMOX.FOR  Fortran program to convert the single zone histories into the common
format employed in the IFPE Database
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: MOX, fissile materials disposition program, fuel performance, post-irradiation examination.