last modified: 31-OCT-2006 | catalog | categories | new | search |

NEA-1772 IFPE/IFA-597-MOX.

IFPE/IFA-597-MOX, Hollow and solid MOX rods experiments

top ]
1. NAME OF EXPERIMENT:  IFPE/IFA-597-MOX.
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/IFA-597-MOX NEA-1772/01 Arrived 31-OCT-2006

Machines used:

Package ID Orig. computer Test computer
NEA-1772/01 Many Computers
top ]
3. DESCRIPTION

A series of tests, containing two MIMAS-MOX fuel rods, both equipped with a fuel centre thermocouple and a pressure bellows transducer, has been irradiated in the Halden Reactor since July 1997 under HBWR conditions. The objectives of the test series were to study the thermal and fission gas release (FGR) behaviour of MOX fuel and to explore potential differences in behaviour between solid and hollow pellets. One of the rods had mainly solid pellets, while the other contained only hollow pellets. Both rods had an initial Pu-fissile enrichment of 6.07%. The cladding outside diameter was 9.50 mm, and the initial fuel-clad gap was 180microns.
In the course of the test, power upratings for FGR studies of the MOX fuel were planned at burnup intervals of about 10 MWd/kgMOX. The power uprating was successfully performed at ~10 MWd/kgMOX, where the fuel peak temperature of the solid pellets exceeded the FGR threshold temperature for UO2 fuel, while that of the hollow pellets remained below the threshold. For the solid fuel, the temperature at onset of FGR was consistent with the empirical threshold temperature for UO2 fuel. For the hollow fuel, gas release was observed at temperatures below the threshold. FGRs at the end-of-life were ~17% for the solid pellet rod and ~14% for the hollow pellet rod, respectively.
The observed FGR has been higher than expected, and as a result of discussions in HPG meetings, IFA-597.7 was unloaded in January 2002. PIE was carried out to check in-pile pressure measurements and examine fuel structural characteristics. The discharge burn-up of the MOX fuel was 32 MWd/kgMOX as determined from in-pile power data.
top ]
9. STATUS
Package ID Status date Status
NEA-1772/01 31-OCT-2006 Arrived restricted
top ]
10. REFERENCES
NEA-1772/01, included references:
- Hisashi Koike:
The MOX Fuel Behaviour Test IFA-597.4/.5/.6/.7: Summary of In-Pile Fuel
Temperatures and Gas Release Data (HWR-729, November 2003)
- Terje Tverberg:
Mixed-oxide (MOX) Fuel Performance Benchmark - Summary of the Results for the
Halden Reactor Project MOX Rods (2007), compiled by Terje Tverberg, OECD Halden
Reactor Project, work carried out within the Expert Group on Reactor-based
Plutonium Disposition (TFRPD), published on 21-JUN-07, 64 pages, ISBN:
978-92-64-99019-7, NEA/NSC/DOC(2007)6
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

Data supplied by:
Mr. Terje TVERBERG
Institutt for Energiteknikk
OECD Halden Reactor Project
P.O. Box 173
N-1751 HALDEN
NORWAY
  
Compilation: J.A. Turnbull, UK
top ]
16. MATERIAL AVAILABLE
NEA-1772/01
HRP-spec04.doc  WORD file including pre-characterization
Rod1.HIS        Irradiation history for rod 1
Rod2.HIS        Irradiation history for rod 2
QA report for compiling dataset
hwr-729.pdf     Documentation
nsc-doc2007-6.pdf Documentation
Readme file
top ]
17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: MOX, burnup, fission gas release, fuels.