International Criticality Safety Benchmark Evaluation Project (ICSBEP)

Evaluations by country: France

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Evaluation ID Laboratory Evaluation Title Year Cases
PU-SOL-THERM-012 Valduc CRITICALITY OF PLUTONIUM NITRATE SOLUTION IN A LARGE WATER-REFLECTED CUBIC TANK (130 x 130 x 100 cm) (19% 240 Pu) 1995 23
PU-SOL-THERM-013 Valduc INTERACTING CYLINDERS OF 256-mm DIAMETER WITH PLUTONIUM NITRATE SOLUTION (115.1g Pu/l) IN AIR 1996 22
PU-SOL-THERM-014 Valduc INTERACTING CYLINDERS OF 300-mm DIAMETER WITH PLUTONIUM NITRATE SOLUTION (115.1g Pu/l) IN AIR 1997 35
PU-SOL-THERM-015 Valduc INTERACTING CYLINDERS OF 300-mm DIAMETER WITH PLUTONIUM NITRATE SOLUTION (152.5g Pu/l) IN AIR 1997 17
PU-SOL-THERM-016 Valduc INTERACTING CYLINDERS OF 300-mm AND 256-mm DIAMETERS WITH PLUTONIUM NITRATE SOLUTION (152.5 and 115.1g Pu/l) AND NITRIC ACID (2N) IN AIR 1997 11
PU-SOL-THERM-017 Valduc INTERACTING CYLINDERS OF 256-mm AND 300-mm DIAMETERS WITH PLUTONIUM NITRATE SOLUTION (115.1g Pu/l) IN AIR 1997 18
PU-SOL-THERM-019 Saclay PLUTONIUM SULFATE SOLUTIONS REFLECTED BY BERYLLIUM OXIDE AND GRAPHITE PROSERPINE REACTOR - SACLAY 2006 11
PU-SOL-THERM-022 Valduc PLUTONIUM (19% 240Pu) NITRATE SOLUTION IN A WATER-REFLECTED ANNULAR CYLINDER TANK (50/20 CM DIA.) 1996 17
PU-SOL-THERM-023 Valduc PLUTONIUM (33.89% and 4.23% 240 Pu) NITRATE SOLUTIONS IN TWO WATER-REFLECTED CYLINDRIC CONCENTRIC TANKS 1998 34
PU-SOL-THERM-027 Valduc MIXED-OXIDE RAPSODIE FUEL-PIN ARRAYS MODERATED BY CONCENTRATED PLUTONIUM NITRATE SOLUTION (19.7 TO 194g Pu/l) AND REFLECTED BY WATER 2003 29
PU-SOL-THERM-028 Valduc WATER-REFLECTED ANNULAR CYLINDERS (50/30 CM DIAM.) CONTAINING PLUTONIUM (3% 240PU) NITRATE SOLUTIONS 2004 18
PU-SOL-THERM-029 Valduc INTERACTING (WATER-REFLECTED OR NOT) ANNULAR CYLINDERS (50/30 CM DIAM.) CONTAINING PLUTONIUM (3% 240PU) NITRATE SOLUTION 2004 20
PU-SOL-THERM-030 Valduc WATER-REFLECTED ANNULAR CYLINDERS (50/20 cm diam.) CONTAINING PLUTONIUM (1.5% 240Pu) NITRATE SOLUTIONS 2006 17
PU-SOL-THERM-031 Valduc PLUTONIUM (19% 240PU) NITRATE SOLUTION IN A WATER-REFLECTED PARALLELEPIPED TANK (50X50 CM SIDE) POISONED BY AN ARRAY OF HAFNIUM PLATES 2011 20
PU-SOL-THERM-032 Valduc WATER-REFLECTED ANNULAR CYLINDERS (50/20 cm diam.) CONTAINING PLUTONIUM (9.95% 240Pu) NITRATE SOLUTIONS 2005 17
PU-SOL-THERM-033 Valduc WATER-REFLECTED CYLINDERS OF PLUTONIUM (3.13 OR 4.23% 240Pu) NITRATE SOLUTIONS, POISONED WITH BORATED PYREX TUBES OR RASCHIG RINGS AND NOT POISONED 2005 63
PU-SOL-THERM-038 Valduc PLUTONIUM TEMPERATURE EFFECT PROGRAM - LOW CONCENTRATED (20, 15 OR 14.3 G/L) PLUTONIUM NITRATE SOLUTIONS AT ROOM TEMPERATURE 2012 5
PU-SOL-THERM-039 Valduc PLUTONIUM TEMPERATURE EFFECT PROGRAM - LOW CONCENTRATED (20, 15 OR 14.3 G/L) PLUTONIUM NITRATE SOLUTIONS AT TEMPERATURES VARYING FROM 28°C TO 40°C 2013 12
PU-SOL-THERM-040 Valduc ARRAYS OF UO2-PuO2 PHENIX PINS CONTAINING 26 wt% OF PLUTONIUM (240Pu/Pu=16 wt%) IN A PLUTONIUM (240Pu/Pu=19 wt%) NITRATE SOLUTION 2014 24
HEU-MET-FAST-080 Valduc BARE, HIGHLY ENRICHED URANIUM FAST BURST REACTOR CALIBAN 2007 1
HEU-MET-THERM-011 Valduc ARRAYS OF PLATES OF URANIUM (93% ENRICHED) ALUMINIUM ALLOY, WATER-MODERATED AND WATER-REFLECTED 2002 43
HEU-SOL-INTER-002 Valduc MIXTURE OF URANIUM (93%) HEXAFLUORIDE AND HYDROFLUORIC ACID (LOW H/U RATIO) IN A HOT-WATER-REFLECTED SPHERICAL TANK 2001 6
HEU-SOL-THERM-039 Valduc MIXTURE OF URANIUM (93%) HEXAFLUORIDE AND HYDROFLUORIC ACID (LOW H/U RATIO) IN A HOT-WATER-REFLECTED SPHERICAL TANK 2001 6
HEU-SOL-THERM-046 Saclay HIGHLY ENRICHED URANIUM (89.84 wt.% 235U) SULFATE SOLUTIONS REFLECTED BY BERYLLIUM OXIDE AND GRAPHITE PROSERPINE REACTOR - SACLAY 2007 13
LEU-MET-THERM-006 Valduc LOW-ENRICHED URANIUM (1.6% 235U) METAL TUBE ARRAYS WATER-MODERATED AND WATER-REFLECTED BUGEY PROGRAM 2004 42
LEU-COMP-THERM-007 Valduc WATER-REFLECTED 4.738-WT.%-ENRICHED URANIUM DIOXIDE FUEL-ROD ARRAYS 1995 10
LEU-COMP-THERM-027 Valduc WATER-MODERATED AND LEAD-REFLECTED 4.738%-WT.%-ENRICHED URANIUM DIOXIDE ROD ARRAYS 1996 4
LEU-COMP-THERM-029 Valduc WATER-MODERATED AND WATER-REFLECTED 4.738-WT.%-ENRICHED URANIUM DIOXIDE ROD ARRAYS SURROUNDED BY HAFNIUM PLATES 1997 12
LEU-COMP-THERM-034 Valduc FOUR 4.738-WT.%-ENRICHED URANIUM DIOXIDE ROD ASSEMBLIES CONTAINED IN CADMIUM, BORATED STAINLESS STEEL, OR BORAL SQUARE CANISTERS, WATER-MODERATED AND -REFLECTED 1998 26
LEU-COMP-THERM-037 Valduc WATER-MODERATED AND PARTIALLY CONCRETE-REFLECTED 4.738-WT.%-ENRICHED URANIUM DIOXIDE ROD ARRAYS 1999 44
LEU-COMP-THERM-038 Valduc WATER-MODERATED 4.738-WT.%-ENRICHED URANIUM DIOXIDE ROD ARRAYS NEXT TO A BORATED CONCRETE SCREEN 1999 14
LEU-COMP-THERM-039 Valduc INCOMPLETE ARRAYS OF WATER-REFLECTED 4.738-WT.%-ENRICHED URANIUM DIOXIDE FUEL-ROD ARRAYS 1999 17
LEU-COMP-THERM-040 Valduc FOUR 4.738-WT.%-ENRICHED URANIUM DIOXIDE ROD ASSEMBLIES CONTAINED IN BORATED STAINLESS STEEL OR BORAL SQUARE CANISTERS, WATER MODERATED AND REFLECTED BY LEAD OR STEEL 1999 10
LEU-COMP-THERM-041 Cadarache STORAGE ARRAYS OF 3%-ENRICHED LWR ASSEMBLIES: THE CRISTO II EXPERIMENT IN THE EOLE REACTOR 1999 5
LEU-COMP-THERM-049 Valduc MARACAS PROGRAMME: POLYTHENE-REFLECTED CRITICAL CONFIGURATIONS WITH LOW-ENRICHED AND LOW-MODERATED URANIUM DIOXIDE POWDER, U(5)O2 1999 18
LEU-COMP-THERM-050 Valduc 149SM SOLUTION TANK IN THE MIDDLE OF WATER-MODERATED 4.738-WT.%-ENRICHED URANIUM DIOXIDE ROD ARRAYS 2000 18
LEU-COMP-THERM-052 Valduc URANIUM DIOXIDE (4.738-WT.%-ENRICHED) FUEL ROD ARRAYS MODERATED AND REFLECTED BY GADOLINIUM NITRATE SOLUTION 2000 6
LEU-COMP-THERM-057 Valduc 4.738-WT.%-ENRICHED URANIUM DIOXIDE FUEL ROD ARRAYS REFLECTED BY WATER IN A DRY STORAGE CONFIGURATION 2010 36
LEU-COMP-THERM-071 Valduc LOW MODERATED 4.738-WT.%-ENRICHED URANIUM DIOXIDE FUEL ROD ARRAYS 2007 4
LEU-COMP-THERM-072 Valduc UNDER-MODERATED 4.738-WT.%-ENRICHED URANIUM DIOXIDE FUEL ROD ARRAYS REFLECTED BY WATER OR POLYETHYLENE 2008 9
LEU-COMP-THERM-073 Valduc WATER-REFLECTED UNDER-MODERATED 4.738-WT.%-ENRICHED URANIUM DIOXIDE FUEL ROD ARRAYS WITH HETEROGENEITIES 2009 16
LEU-COMP-THERM-074 Valduc MIRTE PROGRAM FOUR 4.738-WT.%-ENRICHED URANIUM DIOXIDE FUEL ROD ARRAYS IN WATER SEPARATED BY A CROSS SHAPED SCREEN OF TITANIUM (5-MM AND 10-MM THICK) 2011 4
MIX-SOL-THERM-006 Valduc MIXED URANIUM (70%) PLUTONIUM (30%) NITRATE SOLUTION POISONED WITH GADOLINIUM 2003 20
MIX-SOL-THERM-009 Valduc ARRAYS OF UO2-PuO2 PHENIX PINS CONTAINING 26 wt.% OF PLUTONIUM (240Pu/Put=16 wt.%) IN A MIXED URANIUM-PLUTONIUM (Pu/(U+Pu)=29.7 wt.%, 240Pu/Pu=19 wt.% ) NITRATE SOLUTION 2013 22
MIX-COMP-INTER-005 Cadarache UNDERMODERATED MOX (11 wt.% PUO2) LATTICE IN THE EOLE REACTOR 2005 1
MIX-COMP-THERM-011 Valduc MIXED OXIDE RAPSODIE FUEL-PIN ARRAYS MODERATED AND REFLECTED BY WATER 2001 6
MIX-COMP-THERM-017 Valduc WATER-MODERATED AND WATER-REFLECTED PHENIX PIN (UO2-PUO2; PU/(U+PU)=26%, 240PU=16%) ARRAYS 2012 19
MIX-MISC-THERM-002 Valduc MIXED OXIDE RAPSODIE FUEL PIN ARRAYS MODERATED BY DILUTE PLUTONIUM NITRATE SOLUTION (9.89, 10.07, OR 19.6 g Pu/l) AND REFLECTED BY WATER 2002 12
MIX-MISC-THERM-003 Valduc MIXED-OXIDE RAPSODIE FUEL-PIN ARRAYS MODERATED BY CONCENTRATED PLUTONIUM NITRATE SOLUTION (19.7 TO 194g Pu/l) AND REFLECTED BY WATER 2003 29
MIX-MISC-THERM-006 Valduc ARRAYS OF UO2-PuO2 PHENIX PINS CONTAINING 26 wt.% OF PLUTONIUM (240Pu/Put=16 wt.%) IN A MIXED URANIUM-PLUTONIUM (Pu/(U+Pu)=29.7 wt.%, 240Pu/Pu=19 wt.% ) NITRATE SOLUTION 2013 22
MIX-MISC-THERM-007 Valduc ARRAYS OF UO2-PuO2 PHENIX PINS CONTAINING 26 wt% OF PLUTONIUM (240Pu/Pu=16 wt%) IN A PLUTONIUM (240Pu/Pu=19 wt%) NITRATE SOLUTION 2014 24

Last reviewed: 26 November 2015