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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