Regular European Interlaboratory Measurement Evaluation Programme (REIMEP) was started by IRMM in 1982 for carrying out external control of the quality of the measurements of the nuclear fuel cycle materials. In REIMEP campaigns samples matching materials analysed routinely in the nuclear fuel cycle are sent to participating laboratories for measurements and to date 16 REIMEP campaigns have been organised, which involved safeguards laboratories throughout the world. This awareness programme has made a most significant contribution towards instilling a common European measurement system in the specific field of nuclear safeguards.
Campaigns
| Campaign |
Description |
Status |
Period |
Report |
| REIMEP-18 |
isotopic abundances of low-enriched uranium in nitrate solutions |
completed |
2006 |
certification report EUR 22233 EN[1966Kb]
report to participants EUR 22529 EN[1004Kb] |
| REIMEP-17 |
Plutonium and uranium amount content, and isotope amount ratios in synthetic input solution |
open |
2013-2014 |
|
| REIMEP-16 |
isotopic abundances of plutonium in plutonium nitrate samples |
completed |
2003-2004 |
report to participants EUR 21652 EN[1587Kb] |
| REIMEP-15 |
isotopic abundances of low-enriched and depleted uranium in UF6 |
completed |
2000-2001 |
|
| REIMEP-14 |
isotope content of uranium in uranium nitrate |
completed |
1994-1997 |
|
| REIMEP-13 |
isotope content of uranium in uranium oxide |
completed |
1994-1997 |
|
| REIMEP-12 |
uranium/plutonium in synthetic input solutions |
completed |
1991-1994; 1991-1994 |
|
| REIMEP-11 |
uranium in HEU oxide |
|
| |
| REIMEP-10 |
uranium pellet |
completed |
1989-1991 |
|
| REIMEP-9 |
uranium/plutonium in nitrate solution |
completed |
1991-1994 |
|
| REIMEP-8 |
uranium in nitrate solution |
completed |
1989-1991 |
|
| REIMEP-7 |
uranium in powder |
completed |
1989-1991 |
|
| REIMEP-6 |
uranium in a MOX pellet |
completed |
1991-1994 |
|
| REIMEP-5 |
uranium in UF6 |
completed |
1992-1994 |
|
| REIMEP-4 |
plutonium in oxide |
completed |
1986-1987 |
|
| REIMEP-3 |
uranium in UF6 |
completed |
1986-1987 |
|
MOX: mixed oxides fuel (UO2+ PuO2); HEU: highly enriched uranium