Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1774 IFPE/FMDP-MOX4-5.
last modified: 29-JAN-2007 | catalog | 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)

top ]
1. NAME OF EXPERIMENT

IFPE/FMDP-MOX4-5

top ]
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/FMDP-MOX4-5 NEA-1774/01 Arrived 29-JAN-2007

Machines used:

Package ID Orig. computer Test computer
NEA-1774/01 Many Computers
top ]
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.

top ]
9. STATUS
Package ID Status date Status
NEA-1774/01 29-JAN-2007 Masterfiled restricted
top ]
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)
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
15. 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

 

Compilation: J.A. Turnbull

 

For the OECD/NEA Expert Group on Reactor-Based Plutonium Disposition (TFRPD).

top ]
16. MATERIAL AVAILABLE
NEA-1774/01
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
WMOX.FOR Fortran program to convert the single zone histories into the common
format employed in IFPE
PIE.doc File summarizing the data measured during PIE
FMDP_Benchmark_PROPOSAL_final Summary of the experiment
3A.9.Ott_Paper.pdf Pdf file summarizing the experiment
Pre-characterization.doc File summarizing details of fuel, cladding and fuel
pins
QA report for compiling dataset
Readme file
top ]
17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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