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Table 2.

Characteristics of the considered samples and assemblies

Sample Burnup Enrichment Cooling time Fuel Reactor
MWd/kg wt% Years Type Type
BM1 47 2.36 5 − 7 MOX PWR
BM3 47 2.36 3 − 7 MOX PWR
GU1 59 3.5 3 − 6 UO2 PWR
GU3 52 4.1 1.6 − 2.3 UO2 PWR
U1 34 4.1 7 − 9 UO2 PWR
SF95-5 30 4.11 4 (0) UO2 PWR
SF95-4 37 4.11 4 (0) UO2 PWR
S1.PWR 51 4.0 UO2 PWR
B23-A1-I2680 27 2.53 3 (0) UO2 BWR
B23-C5-K2680 23 2.53 3 (0) UO2 BWR
ENRESA-1 50 3.95 4 UO2 BWR
ENRESA-2 51 3.95 4 UO2 BWR
ENRESA-3 50 3.95 4 UO2 BWR
ENRESA-4 51 3.95 4 UO2 BWR
ENRESA-5 44 3.95 4 UO2 BWR
ENRESA-6 43 3.95 4 UO2 BWR
ENRESA-7 49 3.95 4 UO2 BWR
ENRESA-8 38 3.95 4 UO2 BWR
CLAB-2006 (71 cases) 20 − 51 2.1 − 3.4 13 − 27 UO2 PWR
CLAB-2006 (81 cases) 15 − 47 2.1 − 3.2 11 − 27 UO2 BWR
GE-Morris (14 cases) 27 − 39 3.4 − 4.0 3 − 8 UO2 PWR
GE-Morris (96 cases) 2 − 11 1.1 − 2.5 5 − 28 UO2 BWR
HEDL (6 cases) 26 − 29 2.6 2 − 6 UO2 PWR

In the case of MOX samples, the enrichment concerns the fissile isotopes of the three elements U, Pu and Am; for UO2 samples, the enrichment is given for 235U. The sample burnup values are indicative (and based on the 148Nd inventory for the PIE samples). Cooling times with “(0)” indicates that the reported measurements were adjusted to the discharged time.

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