ICSBEP participants

Ongoing

Participants

Argentina

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
IEU-COMP-THERM-014	Centro Atómico Bariloche	RA-6 REACTOR: WATER REFLECTED, WATER MODERATED U(19.77)3Si2-Al FUEL PLATES	2010	1

Brazil

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
LEU-COMP-THERM-043	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH A HEAVY SS-304 REFLECTOR	2008	9
LEU-COMP-THERM-044	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO2, STAINLESS STEEL AND COPPER RODS	2008	10
LEU-COMP-THERM-046	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR CONSIDERING TEMPERATURE VARIATION FROM 14°C TO 85°C	2011	22
LEU-COMP-THERM-054	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO2, AND UO2-Gd2O3 RODS	2009	8
LEU-COMP-THERM-058	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH LARGE VOID IN THE REFLECTOR	2010	9
LEU-COMP-THERM-067	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR COMPOSED OF FUEL AND MOLYBDENUM RODS	2015	4
LEU-COMP-THERM-077	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR	2004	5
LEU-COMP-THERM-082	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH LOW ENRICHED FUEL AND BURNABLE POISON RODS	2005	6
LEU-COMP-THERM-083	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH A BIG CENTRAL VOID	2005	3
LEU-COMP-THERM-084	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH A CENTRAL CRUCIFORM ROD	2005	1
LEU-COMP-THERM-088	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH HEAVY REFLECTORS COMPOSED OF CARBON STEEL AND NICKEL	2013	36
LEU-COMP-THERM-089	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO2 AND BORATED STAINLESS STEEL PLATES	2006	4
LEU-COMP-THERM-090	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO2 AND STAINLESS STEEL RODS	2006	9
LEU-COMP-THERM-091	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO2, STAINLESS STEEL AND GD2O3 RODS	2007	9
LEU-COMP-THERM-092	IPEN	CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH SOLUBLE BORON	2012	6
SUB-LEU-COMP-THERM-002	IPEN	SUBCRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR	2014	23

Canada

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
LEU-MET-THERM-003	CRL	ZED-2 REACTOR: NATURAL-URANIUM METAL FUEL ASSEMBLIES IN HEAVY-WATER	2012	3

China

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
LEU-MET-THERM-003	CRL	ZED-2 REACTOR: NATURAL-URANIUM METAL FUEL ASSEMBLIES IN HEAVY-WATER	2012	3

Czechia

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
LEU-COMP-THERM-086	NRI	VVER PHYSICS EXPERIMENTS: HEXAGONAL LATTICES (1.275 CM PITCH) OF LOW ENRICHED U(3.6, 4.4 WT.% 235U)O2 FUEL ASSEMBLIES IN LIGHT WATER WITH H3BO3	2006	10
LEU-COMP-THERM-087	NRI	VVER PHYSICS EXPERIMENTS: HEXAGONAL LATTICES (1.22-CM PITCH) OF LOW-ENRICHED U(3.6, 4.4 WT.% U235)O2 FUEL ASSEMBLIES IN LIGHT WATER WITH VARIABLE FUEL-ASSEMBLY PITCH	2008	25

France

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
LEU-COMP-THERM-106	Valduc	4.738-WT.%-ENRICHED-URANIUM-DIOXIDE-FUEL-ROD ARRAYS IN WATER, REFLECTED OR SEPARATED BY VARIOUS STRUCTURAL MATERIALS (SODIUM CHLORIDE, RHODIUM, PVC, MOLYBDENUM, CHROMIUM, MANGANESE)	2021	6
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

Germany

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
LEU-COMP-THERM-081	ANEX	PWR TYPE UO2 FUEL RODS WITH ENRICHMENTS OF 3.5 AND 6.6 WT.% WITH BURNABLE ABSORBER (“OTTO HAHN” NUCLEAR SHIP PROGRAM, SECOND CORE)	2007	1

Hungary

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
LEU-COMP-THERM-015	KFKI	THE VVER EXPERIMENTS: REGULAR AND PERTURBED HEXAGONAL LATTICES OF LOW-ENRICHED UO2 FUEL RODS IN LIGHT WATER	1996	165
LEU-COMP-THERM-036	KFKI	THE VVER EXPERIMENTS: REGULAR AND PERTURBED HEXAGONAL LATTICES OF LOW-ENRICHED UO2 FUEL RODS IN LIGHT WATER - Part 2	1999	69

India

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
PU-COMP-FAST-004	BARC	PURNIMA-I: A PLUTONIUM OXIDE FAST REACTOR WITH AXIAL MOLYBDENUM AND RADIAL COPPER AND MILD STEEL REFLECTORS	2012	1
U233-MET-THERM-001	IGCAR	KALPAKKAM MINI (KAMINI) REACTOR: BERYLLIUM-OXIDE-REFLECTED WATER-MODERATED 233U-FUELED REACTOR	2006	1
U233-SOL-THERM-007	BARC	PURNIMA-II: U-233URANYL NITRATE SOLUTION REACTOR WITH BERYLLIUM OXIDE REFLECTOR	2008	6

Israel

N/A

Japan

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
LEU-MET-THERM-005	Kyoto University	EVALUATION OF THE KYOTO UNIVERSITY CRITICAL ASSEMBLY ERBIUM OXIDE EXPERIMENTS	2012	5
LEU-SOL-THERM-004	JAEA	STACY: WATER-REFLECTED 10%-ENRICHED URANYL NITRATE SOLUTION IN A 60-CM-DIAMETER CYLINDRICAL TANK	1998	7
LEU-SOL-THERM-007	JAEA	STACY: UNREFLECTED 10%-ENRICHED URANYL NITRATE SOLUTION IN A 60-CM-DIAMETER CYLINDRICAL TANK	1999	5
LEU-SOL-THERM-008	JAEA	STACY: 60-CM-DIAMETER CYLINDERS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS REFLECTED WITH CONCRETE	1999	4
LEU-SOL-THERM-009	JAEA	STACY: 60-CM-DIAMETER CYLINDERS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS REFLECTED WITH BORATED CONCRETE	1999	3
LEU-SOL-THERM-010	JAEA	STACY: 60-CM-DIAMETER CYLINDERS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS REFLECTED WITH POLYETHYLENE	1999	4
LEU-SOL-THERM-011	JAEA	STACY: 80-CM-DIAMETER CYLINDRICAL TANK OF 6%-ENRICHED URANYL NITRATE SOLUTIONS	2009	13
LEU-SOL-THERM-016	JAEA	STACY: 28-CM-THICK SLABS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS, WATER-REFLECTED	2000	7
LEU-SOL-THERM-017	JAEA	STACY: 28-CM-THICK SLABS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS, UNREFLECTED	2000	6
LEU-SOL-THERM-018	JAEA	STACY: 28-CM-THICK SLABS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS REFLECTED WITH CONCRETE	2001	6
LEU-SOL-THERM-019	JAEA	STACY: 28-CM-THICK SLABS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS REFLECTED WITH POLYETHYLENE	2001	6
LEU-SOL-THERM-020	JAEA	STACY: 80-CM-DIAMETER CYLINDRICAL TANK OF 10%-ENRICHED URANYL NITRATE SOLUTIONS, WATER-REFLECTED	2001	4
LEU-SOL-THERM-021	JAEA	STACY: 80-CM-DIAMETER CYLINDRICAL TANK OF 10%-ENRICHED URANYL NITRATE SOLUTIONS, UNREFLECTED	2001	4
LEU-SOL-THERM-022	JAEA	STACY: 28-CM-THICK SLABS OF 10%-ENRICHED URANYL NITRATE SOLUTIONS REFLECTED WITH BORATED CONCRETE	2002	4
LEU-SOL-THERM-023	JAEA	STACY: TWO INTERACTING SLAB CORES OF 10%-ENRICHED URANYL NITRATE SOLUTION WITHOUT NEUTRON ISOLATOR	2003	9
LEU-SOL-THERM-024	JAEA	STACY: TWO INTERACTING SLAB CORES OF 10% 235U-ENRICHED URANYL NITRATE SOLUTION WITH POLYETHYLENE NEUTRON ISOLATOR	2004	7
LEU-SOL-THERM-025	JAEA	STACY: TWO INTERACTING SLAB CORES OF 10%-235U-ENRICHED URANYL NITRATE SOLUTION WITH CONCRETE NEUTRON ISOLATOR	2005	7
LEU-COMP-THERM-006	JAEA	CRITICAL ARRAYS OF LOW-ENRICHED UO2 FUEL RODS WITH WATER-TO-FUEL VOLUME RATIOS RANGING FROM 1.5 TO 3.0	1996	18
LEU-COMP-THERM-035	JAEA	CRITICAL ARRAYS OF LOW-ENRICHED UO2 FUEL RODS IN WATER WITH SOLUBLE GADOLINIUM OR BORON POISON	1998	3
LEU-COMP-THERM-062	JAEA	2.6%-ENRICHED UO2 RODS IN LIGHT-WATER MODERATOR WITH BORATED STAINLESS STEEL PLATE: SINGLE ARRAYS	2002	15
LEU-COMP-THERM-065	JAEA	CRITICAL CONFIGURATIONS OF 2.6%-ENRICHED UO2 ROD ARRAYS IN LIGHT-WATER MODERATOR WITH BORATED STAINLESS STEEL PLATE: COUPLED ARRAYS	2003	17
LEU-COMP-THERM-093	PNC	DEUTERIUM CRITICAL ASSEMBLY WITH 1.2% ENRICHED URANIUM VARYING COOLANT VOID FRACTION AND LATTICE PITCH	2006	10
LEU-MISC-THERM-001	JAEA	STACY HETEROGENEOUS CORES: A 60-CM-DIAMETER TANK CONTAINING 5%-ENRICHED UO2 FUEL RODS IN 6%-ENRICHED URANYL NITRATE SOLUTIONS, WATER-REFLECTED	2004	5
LEU-MISC-THERM-002	JAEA	STACY: A 60-CM-DIAMETER TANK CONTAINING 5%-ENRICHED UO2 FUEL RODS (2.1-CM SQUARE LATTICE PITCH) IN 6%-ENRICHED URANYL NITRATE SOLUTIONS, UNREFLECTED	2005	6
LEU-MISC-THERM-003	JAEA	STACY: A 60-CM-DIAMETER TANK CONTAINING 5%-ENRICHED UO2 FUEL RODS (1.5-CM SQUARE LATTICE PITCH) IN 6%-ENRICHED URANYL NITRATE SOLUTIONS	2007	15
LEU-MISC-THERM-005	JAEA	STACY: A 60-CM-DIAMETER WATER-REFLECTED TANK CONTAINING 5%-ENRICHED UO2 FUEL RODS (1.5-CM SQUARE LATTICE PITCH) IN 6%-ENRICHED URANYL NITRATE SOLUTIONS POISONED WITH PSEUDO-FISSION-PRODUCT ELEMENTS	2008	12
LEU-MISC-THERM-006	JAEA	STACY: A 60-CM-DIAMETER TANK CONTAINING 5%-ENRICHED UO2 FUEL RODS (1.5-CM SQUARE LATTICE PITCH) IN 6%-ENRICHED URANYL NITRATE SOLUTIONS POISONED WITH GADOLINIUM, UNREFLECTED AND WATER-REFLECTED	2009	10
LEU-MISC-THERM-007	JAEA	STACY: A 60-CM-DIAMETER TANK CONTAINING 5%-ENRICHED UO2 FUEL RODS (2.5-CM SQUARE LATTICE PITCH) IN 6%-ENRICHED URANYL NITRATE SOLUTIONS, UNREFLECTED AND WATER-REFLECTED	2010	12
MIX-COMP-THERM-004	JAEA	CRITICAL ARRAYS OF MIXED PLUTONIUM-URANIUM FUEL RODS WITH WATER-TO-FUEL VOLUME RATIOS RANGING FROM 2.4 TO 5.6	1997	11

Kazakhstan

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
HEU-COMP-THERM-016	Semipalatinsk Nuclear Test Site	IGR REACTOR – URANIUM-GRAPHITE BLOCKS REFLECTED BY GRAPHITE	2000	6

Poland

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
HEU-MET-THERM-026	IAE	BERYLLIUM-MODERATED, GRAPHITE-REFLECTED CRITICAL EXPERIMENTS OF HIGHLY ENRICHED URANIUM TUBULAR FUEL	2006	27

Korea

N/A

Russia

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
PU-MET-FAST-012	IPPE	URANIUM-REFLECTED ARRAY OF PLUTONIUM FUEL RODS	1996	1
PU-MET-FAST-013	IPPE	COPPER-REFLECTED ARRAY OF PLUTONIUM FUEL RODS	1996	1
PU-MET-FAST-014	IPPE	NICKEL-REFLECTED ARRAY OF PLUTONIUM FUEL RODS	1996	1
PU-MET-FAST-015	IPPE	IRON-REFLECTED ARRAY OF PLUTONIUM FUEL RODS	1996	1
PU-MET-FAST-019	VNIITF	SPHERE OF PLUTONIUM REFLECTED BY BERYLLIUM	1997	1
PU-MET-FAST-020	VNIITF	SPHERE OF PLUTONIUM REFLECTED BY DEPLETED URANIUM	1997	1
PU-MET-FAST-021	VNIITF	BERYLLIUM- AND BERYLLIUM OXIDE-REFLECTED CYLINDERS OF PLUTONIUM	1996	2
PU-MET-FAST-022	VNIIEF	BARE SPHERICAL ASSEMBLY OF 239PU(δ, 98%)	1996	1
PU-MET-FAST-023	VNIIEF	GRAPHITE REFLECTED SPHERICAL ASSEMBLY OF 239PU(δ, 98%)	1996	1
PU-MET-FAST-024	VNIIEF	POLYETHYLENE-REFLECTED SPHERICAL ASSEMBLY OF 239PU(δ, 98%)	1996	1
PU-MET-FAST-025	VNIIEF	SPHERICAL ASSEMBLY OF 239Pu(δ, 98%) WITH 1.55-CM STEEL REFLECTOR	1996	1
PU-MET-FAST-026	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(δ, 98%) WITH 11.9-CM STEEL REFLECTOR	1996	1
PU-MET-FAST-027	VNIIEF	POLYETHYLENE-REFLECTED SPHERICAL ASSEMBLY OF 239PU(δ, 89%)	1996	1
PU-MET-FAST-028	VNIIEF	STEEL-REFLECTED SPHERICAL ASSEMBLY OF 239PU(δ, 89%)	1996	1
PU-MET-FAST-029	VNIIEF	BARE SPHERICAL ASSEMBLY OF 239PU(a, 88%)	1996	1
PU-MET-FAST-030	VNIIEF	GRAPHITE-REFLECTED SPHERICAL ASSEMBLY OF 239PU(a, 88%)	1996	1
PU-MET-FAST-031	VNIIEF	POLYETHYLENE-REFLECTED SPHERICAL ASSEMBLY OF 239PU(a, 88%)	1996	1
PU-MET-FAST-032	VNIIEF	STEEL-REFLECTED SPHERICAL ASSEMBLY OF 239PU(a, 88%)	1996	1
PU-MET-FAST-035	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(δ, 98%) WITH 3.15-CM LEAD REFLECTOR	1998	1
PU-MET-FAST-036	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(δ, 98%) WITH COMPOUND REFLECTOR OF 0.05-CM CADMIUM AND 2.3-CM POLYETHYLENE	1998	1
PU-MET-FAST-039	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(δ, 98%) WITH A 4.25-CM DURALUMIN REFLECTOR	1998	1
PU-MET-FAST-040	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(δ, 98%) WITH A 1.6-CM COPPER REFLECTOR	1998	1
PU-MET-FAST-041	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(a, 88%) WITH A 20.98-CM DEPLETED-URANIUM REFLECTOR	1998	1
PU-MET-FAST-046	IPPE	FAST REACTOR WITH PLUTONIUM METAL FUEL AND MERCURY COOLANT	2008	3
PU-MET-INTER-001	IPPE	CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF PLUTONIUM, SILICON DIOXIDE, AND POLYETHYLENE	2000	6
PU-MET-THERM-001	IPPE	CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF PLUTONIUM, SILICON DIOXIDE, AND POLYETHYLENE	2000	6
PU-MET-MIXED-001	IPPE	CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF PLUTONIUM, SILICON DIOXIDE, AND POLYETHYLENE	2000	6
HEU-MET-FAST-005	IPPE	BERYLLIUM- AND MOLYBDENUM-REFLECTED CYLINDERS OF HIGHLY ENRICHED URANIUM	1996	6
HEU-MET-FAST-008	VNIITF	BARE SPHERE OF HIGHLY ENRICHED URANIUM	1996	1
HEU-MET-FAST-009	VNIITF	SPHERES OF HIGHLY ENRICHED URANIUM REFLECTED BY BERYLLIUM OR BERYLLIUM OXIDE	1996	2
HEU-MET-FAST-010	VNIITF	SPHERES OF HIGHLY ENRICHED URANIUM REFLECTED BY BORON+BERYLLIUM OR BORON+BERYLLIUM OXIDE	1996	2
HEU-MET-FAST-011	VNIITF	SPHERE OF HIGHLY ENRICHED URANIUM REFLECTED BY POLYETHYLENE	1996	1
HEU-MET-FAST-012	VNIITF	SPHERE OF HIGHLY ENRICHED URANIUM REFLECTED BY ALUMINUM	1996	1
HEU-MET-FAST-013	VNIITF	SPHERE OF HIGHLY ENRICHED URANIUM REFLECTED BY STEEL	1996	1
HEU-MET-FAST-014	VNIITF	SPHERE OF HIGHLY ENRICHED URANIUM REFLECTED BY DEPLETED URANIUM	1996	1
HEU-MET-FAST-015	VNIITF	UNREFLECTED CYLINDER OF HIGHLY ENRICHED URANIUM	1996	1
HEU-MET-FAST-016	VNIITF	BERYLLIUM-REFLECTED AND BERYLLIUM OXIDE-REFLECTED CYLINDERS OF HIGHLY ENRICHED URANIUM	1996	2
HEU-MET-FAST-017	VNIITF	BERYLLIUM-MODERATED AND -REFLECTED CYLINDER OF HIGHLY ENRICHED URANIUM	1996	1
HEU-MET-FAST-018	VNIIEF	BARE SPHERICAL ASSEMBLY OF 235U(90%)	1996	1
HEU-MET-FAST-019	VNIIEF	GRAPHITE-REFLECTED SPHERICAL ASSEMBLY OF 235U(90%)	1996	1
HEU-MET-FAST-020	VNIIEF	POLYETHYLENE-REFLECTED SPHERICAL ASSEMBLY OF 235U(90%)	1996	1
HEU-MET-FAST-021	VNIIEF	STEEL-REFLECTED SPHERICAL ASSEMBLY OF 235U(90%)	1996	1
HEU-MET-FAST-022	VNIIEF	DURALUMIN-REFLECTED SPHERICAL ASSEMBLY OF 235U(90%)	1996	1
HEU-MET-FAST-024	VNIITF	SPHERE OF HIGHLY ENRICHED URANIUM REFLECTED BY STEEL AND POLYETHYLENE	1996	1
HEU-MET-FAST-025	VNIITF	FIVE VANADIUM-REFLECTED HEU CYLINDERS	2008	5
HEU-MET-FAST-027	VNIIEF	SPHERICAL ASSEMBLY OF 235U(90%) WITH A 3.25-CM LEAD REFLECTOR	1998	1
HEU-MET-FAST-029	VNIIEF	SPHERICAL ASSEMBLY OF 235U(90%) WITH 4.7-CM DEPLETED-URANIUM REFLECTOR	1997	1
HEU-MET-FAST-030	VNIITF	HETEROGENEOUS CYLINDER OF HIGHLY ENRICHED URANIUM WITH BERYLLIUM MODERATOR AND DEPLETED-URANIUM REFLECTOR	1998	1
HEU-MET-FAST-031	VNIIEF	SPHERICAL ASSEMBLY OF 235U(90%) WITH CENTRAL AREA OF POLYETHYLENE AND 17.45-CM POLYETHYLENE REFLECTOR	1998	1
HEU-MET-FAST-033	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM WITH POLYETHYLENE AND STEEL	1997	2
HEU-MET-FAST-034	VNIITF	THREE HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM WITH POLYETHYLENE AND TITANIUM, ALUMINIUM, OR STEEL	1998	3
HEU-MET-FAST-036	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM WITH POLYETHYLENE AND DEPLETED URANIUM	1998	2
HEU-MET-FAST-037	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND DEPLETED URANIUM WITH POLYETHYLENE OR POLYETHYLENE AND CADMIUM REFLECTOR	1998	2
HEU-MET-FAST-038	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM WITH BERYLLIUM AND BERYLLIUM OXIDE MODERATORS AND DEPLETED-URANIUM REFLECTOR	1998	2
HEU-MET-FAST-040	VNIITF	HETEROGENEOUS VANADIUM DILUTED HEU CYLINDER	2008	1
HEU-MET-FAST-042	VNIITF	TWO HETEROGENEOUS VANADIUM DILUTED AND BERYLLIUM OR BERYLLIUM OXIDE MODERATED HEU CYLINDERS	2008	2
HEU-MET-FAST-043	VNIITF	HEU CYLINDERS AXIALLY REFLECTED BY STEEL	2010	5
HEU-MET-FAST-044	VNIITF	HEU CYLINDERS AXIALLY REFLECTED BY ALUMINUM	2010	5
HEU-MET-FAST-049	VNIITF	THREE HEU CYLINDERS AXIALLY REFLECTED BY TUNGSTEN	2009	3
HEU-MET-FAST-050	VNIITF	HETEROGENEOUS TUNGSTEN-DILUTED HEU CYLINDER	2009	1
HEU-MET-FAST-052	VNIITF	HETEROGENEOUS, TUNGSTEN-DILUTED, BERYLLIUM- AND BERYLLIUM-OXIDE-MODERATED, HEU CYLINDER REFLECTED BY DEPLETED URANIUM	2009	1
HEU-MET-FAST-064	VNIITF	THREE CYLINDERS OF LEAD-REFLECTED HIGHLY ENRICHED URANIUM	2005	3
HEU-MET-FAST-065	VNIITF	UNREFLECTED CYLINDER OF HIGHLY ENRICHED URANIUM - SECOND CONFIGURATION	1996	1
HEU-MET-FAST-068	IPPE	HIGHLY ENRICHED URANIUM, THORIUM, AND POLYETHYLENE ASSEMBLIES (KBR-22 AND KBR-23)	2002	2
HEU-MET-FAST-079	VNIITF	FIVE TITANIUM-REFLECTED HEU CYLINDERS	2006	5
HEU-MET-FAST-082	VNIITF	THREE HEU ASSEMBLIES WITH POLYETHYLENE TOP REFLECTOR	2008	3
HEU-MET-FAST-087	VNIITF	HETEROGENEOUS IRON-DILUTED HEU CYLINDER	2010	1
HEU-MET-FAST-088	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND STEEL WITH POLYETHYLENE REFLECTOR	2011	2
HEU-MET-FAST-089	VNIITF	HETEROGENEOUS ALUMINUM-DILUTED HEU CYLINDER	2010	1
HEU-MET-FAST-090	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND ALUMINUM WITH POLYETHYLENE REFLECTOR	2011	2
HEU-MET-FAST-091	VNIITF	HIGHLY ENRICHED URANIUM CYLINDER REFLECTED BY POLYETHYLENE	2010	1
HEU-MET-FAST-092	VNIITF	FOUR MOLYBDENUM-REFLECTED HEU CYLINDERS	2012	4
HEU-MET-FAST-093	VNIITF	HETEROGENEOUS MOLYBDENUM - DILUTED HEU CYLINDER	2013	1
HEU-MET-FAST-094	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, BERYLLIUM, BERYLLIUM OXIDE, AND MOLYBDENUM REFLECTED BY DEPLETED URANIUM	2013	2
HEU-MET-INTER-005	IPPE	CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF HIGHLY ENRICHED URANIUM, SILICON DIOXIDE, AND POLYETHYLENE	2000	5
HEU-MET-INTER-008	IPPE	HIGHLY ENRICHED URANIUM, THORIUM, AND POLYETHYLENE ASSEMBLIES (KBR-22 AND KBR-23)	2002	2
HEU-MET-THERM-005	IPPE	CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF HIGHLY ENRICHED URANIUM, SILICON DIOXIDE, AND POLYETHYLENE	2000	5
HEU-MET-MIXED-001	VNIITF	HETEROGENEOUS CYLINDER OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND TITANIUM WITH POLYETHYLENE REFLECTOR	1998	1
HEU-MET-MIXED-002	VNIIEF	SPHERICAL ASSEMBLY OF 235U(90%) WITH CENTRAL AREA OF POLYETHYLENE AND 12.85-CM POLYETHYLENE REFLECTOR	1998	1
HEU-MET-MIXED-003	VNIIEF	SPHERICAL ASSEMBLY OF 235U(90%) WITH CENTRAL AREA OF POLYETHYLENE AND 15.85-CM POLYETHYLENE REFLECTOR	1998	1
HEU-MET-MIXED-004	VNIITF	HETEROGENEOUS CYLINDER OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND DEPLETED URANIUM WITH REFLECTOR OF DEPLETED URANIUM	1998	1
HEU-MET-MIXED-005	IPPE	CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF HIGHLY ENRICHED URANIUM, SILICON DIOXIDE, AND POLYETHYLENE	2000	5
HEU-MET-MIXED-006	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM WITH POLYETHYLENE AND STEEL	1997	2
HEU-MET-MIXED-015	VNIITF	HETEROGENEOUS CYLINDER OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND TITANIUM WITH POLYETHYLENE REFLECTOR	2007	1
HEU-MET-MIXED-016	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND VANADIUM WITH POLYETHYLENE REFLECTOR	2008	2
HEU-MET-MIXED-017	VNIITF	HETEROGENEOUS CYLINDER OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND TUNGSTEN WITH POLYETHYLENE REFLECTOR	2009	1
HEU-MET-MIXED-018	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND STEEL WITH POLYETHYLENE REFLECTOR	2011	2
HEU-MET-MIXED-019	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND ALUMINUM WITH POLYETHYLENE REFLECTOR	2011	2
HEU-MET-MIXED-020	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND MOLYBDENUM WITH POLYETHYLENE REFLECTOR	2013	2
HEU-SOL-THERM-014	IPPE	URANIUM NITRATE SOLUTION (70g U/l) WITH GADOLINIUM	1996	3
HEU-SOL-THERM-015	IPPE	URANIUM NITRATE SOLUTION (100g U/l) WITH GADOLINIUM	1996	5
HEU-SOL-THERM-016	IPPE	URANIUM NITRATE SOLUTION (150g U/l) WITH GADOLINIUM	1996	3
HEU-SOL-THERM-017	IPPE	URANIUM NITRATE SOLUTION (200g U/l) WITH GADOLINIUM	1996	9
HEU-SOL-THERM-018	IPPE	URANIUM NITRATE SOLUTION (300 gU/l) WITH GADOLINIUM	1996	12
HEU-SOL-THERM-019	IPPE	URANIUM NITRATE SOLUTION (400 gU/l) WITH GADOLINIUM	1996	3
HEU-SOL-THERM-022	IPPE	WATER-REFLECTED ASSEMBLY OF TWO INTERSECTING STEEL PIPES CONTAINING 90%-ENRICHED URANYL NITRATE WATER SOLUTIONS	1997	1
HEU-SOL-THERM-023	IPPE	WATER-REFLECTED ASSEMBLY OF INTERSECTING STEEL PIPES CONTAINING 90%-ENRICHED URANYL NITRATE WATER SOLUTION	1997	1
HEU-SOL-THERM-024	IPPE	BARE AND WATER-REFLECTED ASSEMBLIES OF INTERSECTING STEEL PIPES CONTAINING 90%-ENRICHED URANYL NITRATE WATER SOLUTIONS	1997	14
HEU-SOL-THERM-025	IPPE	URANIUM NITRATE SOLUTIONS WITH GADOLINIUM	1997	18
HEU-SOL-THERM-027	IPPE	URANIUM (89% 235U) NITRATE SOLUTION WITH CENTRAL BORON CARBIDE OR CADMIUM ABSORBER ROD	1998	9
HEU-SOL-THERM-028	IPPE	URANIUM (89% 235U) NITRATE SOLUTIONS WITH CENTRAL BORON CARBIDE ABSORBER ROD	1998	18
HEU-SOL-THERM-029	IPPE	URANIUM (89% 235U) NITRATE SOLUTION WITH CLUSTER OF SEVEN BORON CARBIDE ABSORBER RODS	1998	7
HEU-SOL-THERM-030	IPPE	URANIUM (89% 235U) NITRATE SOLUTIONS WITH CLUSTER OF SEVERAL BORON CARBIDE ABSORBER RODS	1998	7
HEU-SOL-THERM-031	IPPE	URANIUM (89% 235U) NITRATE SOLUTION WITH 18 OR 36 BORON CARBIDE ABSORBER RODS IN 4.0- OR 6.0-CM-PITCH TRIANGULAR LATTICES	1998	4
HEU-SOL-THERM-035	IPPE	BORON CARBIDE ABSORBER RODS IN URANIUM (89% 235U) NITRATE SOLUTIONS	1998	9
HEU-SOL-THERM-036	IPPE	SQUARE-PITCHED LATTICES OF BORON CARBIDE ABSORBER RODS IN URANIUM (89% 235U) NITRATE SOLUTION	1998	4
HEU-SOL-THERM-037	IPPE	HEXAGONALLY PITCHED LATTICES OF BORON CARBIDE ABSORBER RODS IN URANIUM (89% 235U) NITRATE SOLUTION	1998	9
HEU-COMP-FAST-003	IPPE	HIGHLY ENRICHED URANIUM DIOXIDE CYLINDERS IMMERSED IN MIXTURES OF LIGHT AND HEAVY WATER	1998	23
HEU-COMP-INTER-005	IPPE	K-INFINITY EXPERIMENTS IN INTERMEDIATE NEUTRON SPECTRA FOR VARIOUS STRUCTURAL MATERIALS	1999	5
HEU-COMP-INTER-006	IPPE	HIGHLY ENRICHED URANIUM DIOXIDE CYLINDERS IMMERSED IN MIXTURES OF LIGHT AND HEAVY WATER	1998	23
HEU-COMP-THERM-003	Kurchatov Institute	TWO-ZONE CRITICAL ARRAYS WITH U(80%)O2 + CU FUEL AND LIGHTWATER MODERATOR	1996	15
HEU-COMP-THERM-004	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED LATTICES OF U(90%)O2 + CU FUEL RODS WITH GD OR SM RODS	1996	4
HEU-COMP-THERM-005	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED CLUSTERS OF LATTICES OF U(80%)O2 + CU FUEL RODS	1996	2
HEU-COMP-THERM-006	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED LATTICES OF U(80%)O2 + CU FUEL RODS	1996	3
HEU-COMP-THERM-007	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED DOUBLE LATTICES OF U(80%)O2 + CU FUEL RODS AND ZIRCONIUM HYDRIDE RODS	1996	3
HEU-COMP-THERM-008	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED DOUBLE LATTICES OF U(80%)O2 + CU FUEL RODS AND BORON CARBIDE RODS	1996	2
HEU-COMP-THERM-009	Kurchatov Institute	INTERMEDIATE HETEROGENEOUS ASSEMBLY WITH HIGHLY ENRICHED URANIUM DIOXIDE (96% 235U) AND ZIRCONIUM HYDRIDE MODERATOR	1995	6
HEU-COMP-THERM-011	Kurchatov Institute	EXPERIMENTS WITH FOUR CLUSTERS OF SQUARE-PITCHED 21x21 LATTICES OF HIGHLY ENRICHED (~80% 235U) STAINLESS-STEEL-CLAD FUEL RODS	1998	3
HEU-COMP-THERM-012	Kurchatov Institute	EXPERIMENTS WITH FOUR CLUSTERS OF SQUARE-PITCHED 18x18 LATTICES OF HIGHLY ENRICHED (~80% 235U) STAINLESS-STEEL-CLAD FUEL RODS OF TWO TYPES	1998	2
HEU-COMP-THERM-013	Kurchatov Institute	EXPERIMENTS WITH NINE CLUSTERS OF SQUARE-PITCHED 14x14 LATTICES OF HIGHLY ENRICHED (~80% 235U) STAINLESS-STEEL-CLAD FUEL RODS	1998	2
HEU-COMP-THERM-014	Kurchatov Institute	EXPERIMENTS WITH NINE CLUSTERS OF SQUARE-PITCHED 10x10 LATTICES OF HIGHLY ENRICHED (~80% 235U) STAINLESS-STEEL-CLAD FUEL RODS	1998	2
HEU-COMP-MIXED-002	IPPE	HIGHLY ENRICHED URANIUM DIOXIDE CYLINDERS IMMERSED IN MIXTURES OF LIGHT AND HEAVY WATER	1998	23
HEU-COMP-MIXED-003	Kurchatov Institute	INTERMEDIATE HETEROGENEOUS ASSEMBLY WITH HIGHLY ENRICHED URANIUM DIOXIDE (96% 235U) AND ZIRCONIUM HYDRIDE MODERATOR	1995	6
HEU-COMP-MIXED-004	Kurchatov Institute	INTERMEDIATE HETEROGENEOUS ASSEMBLY WITH HIGHLY ENRICHED URANIUM DIOXIDE AND SAND/WATER RADIAL REFLECTOR	1996	5
IEU-MET-FAST-003	VNIIEF	BARE SPHERICAL ASSEMBLY OF 235U(36%)	1996	1
IEU-MET-FAST-004	VNIIEF	GRAPHITE-REFLECTED SPHERICAL ASSEMBLY OF 235U(36%)	1996	1
IEU-MET-FAST-005	VNIIEF	STEEL-REFLECTED SPHERICAL ASSEMBLY OF 235U(36%)	1996	1
IEU-MET-FAST-006	VNIIEF	DURALUMIN-REFLECTED SPHERICAL ASSEMBLY OF 235U(36%)	1996	1
IEU-MET-FAST-008	VNIIEF	DEPLETED-URANIUM-REFLECTED SPHERICAL ASSEMBLY OF 235U(36%)	1997	1
IEU-MET-FAST-009	VNIIEF	SPHERICAL ASSEMBLY OF 235U(36%) WITH A 5.75-CM POLYETHYLENE REFLECTOR	1998	1
IEU-MET-FAST-017	IPPE	K-INFINITY EXPERIMENTS FOR 238U IN FAST NEUTRON SPECTRA: MEASUREMENTS WITH ENRICHED URANIUM OR PLUTONIUM MIXED WITH DEPLETED URANIUM (BFS-35, BFS-33, BFS-38, BFS-31, AND BFS-42 ASSEMBLIES)	2004	11
IEU-MET-FAST-018	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM WITH POLYETHYLENE AND DEPLETED URANIUM	1998	2
IEU-MET-FAST-023	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND DEPLETED URANIUM WITH POLYETHYLENE OR POLYETHYLENE AND CADMIUM REFLECTOR	1998	2
IEU-MET-MIXED-001	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM WITH POLYETHYLENE AND DEPLETED URANIUM	1998	2
IEU-MET-MIXED-002	VNIITF	TWO HETEROGENEOUS CYLINDERS OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND DEPLETED URANIUM WITH POLYETHYLENE OR POLYETHYLENE AND CADMIUM REFLECTOR	1998	2
IEU-MET-MIXED-003	VNIITF	HETEROGENEOUS CYLINDER OF HIGHLY ENRICHED URANIUM, POLYETHYLENE, AND DEPLETED URANIUM WITH REFLECTOR OF DEPLETED URANIUM	1998	1
IEU-SOL-THERM-001	Kurchatov Institute	GRAPHITE-REFLECTED URANYL SULPHATE (20.9% 235U) SOLUTIONS	1997	4
IEU-COMP-FAST-002	IPPE	K-INFINITY MEASUREMENTS WITH ENRICHED URANIUM MIXED WITH THORIUM AND POLYETHYLENE (KBR-18, KBR-19, KBR-20, AND KBR-21 ASSEMBLIES)	2002	4
IEU-COMP-INTER-001	IPPE	K-INFINITY MEASUREMENTS WITH ENRICHED URANIUM MIXED WITH THORIUM AND POLYETHYLENE (KBR-18, KBR-19, KBR-20, AND KBR-21 ASSEMBLIES)	2002	4
IEU-COMP-INTER-002	IPPE	K-INFINITY EXPERIMENTS FOR 238U IN FAST NEUTRON SPECTRA: MEASUREMENTS WITH ENRICHED URANIUM OR PLUTONIUM MIXED WITH DEPLETED URANIUM (BFS-35, BFS-33, BFS-38, BFS-31, AND BFS-42 ASSEMBLIES)	2004	11
IEU-COMP-THERM-002	IPPE	WATER-MODERATED U(17)O2 ANNULAR FUEL RODS WITHOUT ABSORBER AND WITH GADOLINIUM OR CADMIUM ABSORBERS IN 6.8-CM-PITCH HEXAGONAL LATTICES AT DIFFERENT TEMPERATURES	1998	6
IEU-COMP-THERM-005	IPPE	K-INFINITY MEASUREMENTS WITH ENRICHED URANIUM MIXED WITH THORIUM AND POLYETHYLENE (KBR-18, KBR-19, KBR-20, AND KBR-21 ASSEMBLIES)	2002	4
IEU-COMP-THERM-008	Kurchatov Institute	GRAPHITE ANNULAR CORE ASSEMBLIES WITH SPHERICAL FUEL ELEMENTS CONTAINING COATED UO2 FUEL PARTICLES	2007	5
LEU-SOL-THERM-003	IPPE	FULL AND TRUNCATED BARE SPHERES OF 10% ENRICHED URANYL NITRATE WATER SOLUTIONS	1997	9
LEU-SOL-THERM-005	IPPE	BORON CARBIDE ABSORBER RODS IN URANIUM (5.64% 235U) NITRATE SOLUTION	1998	3
LEU-SOL-THERM-006	IPPE	BORON CARBIDE ABSORBER RODS IN URANIUM (10% 235U) NITRATE SOLUTION	1998	5
LEU-COMP-THERM-019	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED LATTICES OF U(5%)O2 STAINLESS STEEL CLAD FUEL RODS	1997	3
LEU-COMP-THERM-020	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED PARTIALLY FLOODED LATTICES OF U(5%)O2 ZIRCONIUM CLAD FUEL RODS, 1.3-CM PITCH	1997	7
LEU-COMP-THERM-021	Kurchatov Institute	HEXAGONALLY PITCHED PARTIALLY FLOODED LATTICES OF U(5%)O2 ZIRCONIUM CLAD FUEL RODS MODERATED BY WATER WITH BORIC ACID	1997	6
LEU-COMP-THERM-022	Kurchatov Institute	UNIFORM WATER-MODERATED HEXAGONALLY PITCHED LATTICES OF RODS WITH U(10%)O2 FUEL	1998	7
LEU-COMP-THERM-023	Kurchatov Institute	PARTIALLY FLOODED UNIFORM LATTICES OF RODS WITH U(10%)O2 FUEL	1997	6
LEU-COMP-THERM-024	Kurchatov Institute	WATER-MODERATED SQUARE-PITCHED UNIFORM LATTICES OF RODS WITH U(10%)O2 FUEL	1997	2
LEU-COMP-THERM-025	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED LATTICES OF U(7.5%)O2 STAINLESS-STEEL-CLAD FUEL RODS	1997	4
LEU-COMP-THERM-026	IPPE	WATER-MODERATED U(4.92)O2 FUEL RODS IN 1.29, 1.09, AND 1.01 CM PITCH HEXAGONAL LATTICES AT DIFFERENT TEMPERATURES	1997	6
LEU-COMP-THERM-030	Kurchatov Institute	VVER Physics Experiments: Regular Hexagonal (1.27-cm Pitch) Lattices of Low-Enriched U(3.5 Wt.% 235U)O2 Fuel Rods in Light Water at Different Core Critical Dimensions	2010	12
LEU-COMP-THERM-031	Kurchatov Institute	WATER-MODERATED HEXAGONALLY PITCHED PARTIALLY FLOODED LATTICES OF U(5%)O2 ZIRCONIUM-CLAD FUEL RODS, 0.8-CM PITCH	1997	6
LEU-COMP-THERM-032	Kurchatov Institute	UNIFORM WATER-MODERATED LATTICES OF RODS WITH U(10%)O2 FUEL IN RANGE FROM 20°C TO 274°C	1997	9
LEU-COMP-THERM-053	Kurchatov Institute	VVER PHYSICS EXPERIMENTS: REGULAR HEXAGONAL (1.27 CM PITCH) LATTICES OF LOW-ENRICHED U(4.4 WT.% 235U)O2 FUEL RODS IN LIGHT WATER AT DIFFERENT CORE CRITICAL DIMENSIONS	2007	14
LEU-COMP-THERM-060	Kurchatov Institute	RBMK GRAPHITE REACTOR: UNIFORM CONFIGURATIONS OF U(1.8, 2.0, or 2.4% 235U)O2 FUEL ASSEMBLIES, AND CONFIGURATIONS OF U(2.0% 235U)O2 ASSEMBLIES WITH EMPTY CHANNELS, WATER COLUMNS, AND BORON OR THORIUM ABSORBERS, WITH OR WITHOUT WATER IN CHANNELS	2003	28
LEU-COMP-THERM-061	Kurchatov Institute	VVER PHYSICS EXPERIMENTS: HEXAGONAL (1.27-CM PITCH) LATTICES OF U(4.4 WT.% 235U)O2 FUEL RODS IN LIGHT WATER, PERTURBED BY BORON, HAFNIUM, OR DYSPROSIUM ABSORBER RODS, OR BY WATER GAP WITH/WITHOUT EMPTY ALUMINIUM TUBES	2002	10
LEU-COMP-THERM-064	Kurchatov Institute	VVER PHYSICS EXPERIMENTS: REGULAR HEXAGONAL (1.27 CM PITCH) LATTICES OF LOW-ENRICHED U(2.4 WT.% U-235)O2 FUEL RODS IN LIGHT WATER AT DIFFERENT CORE CRITICAL DIMENSIONS	2011	7
LEU-COMP-THERM-070	Kurchatov Institute	VVER PHYSICS EXPERIMENTS: REGULAR HEXAGONAL (1.10-CM PITCH) LATTICES OF LOW-ENRICHED U(6.5 WT.% 235U)O2 FUEL RODS IN LIGHT WATER AT DIFFERENT CORE CRITICAL DIMENSIONS	2003	12
LEU-COMP-THERM-075	Kurchatov Institute	VVER PHYSICS EXPERIMENTS: HEXAGONAL (1.10 CM PITCH) LATTICES OF LOW-ENRICHED U(6.5 WT.% 235U)O2 FUEL RODS IN LIGHT WATER, PERTURBED BY BORON ABSORBER RODS AND WATER HOLES	2004	6
LEU-COMP-THERM-085	Kurchatov Institute	VVER PHYSICS EXPERIMENTS: REGULAR HEXAGONAL (1.27 CM PITCH) LATTICES OF LOW-ENRICHED U(6.5 WT.% 235U)O2 FUEL RODS IN LIGHT WATER AT DIFFERENT CORE CRITICAL DIMENSIONS	2005	13
LEU-COMP-THERM-094	Kurchatov Institute	VVER PHYSICS EXPERIMENTS: REGULAR HEXAGONAL (1.10 CM PITCH) TWO-REGION LATTICES OF LOW-ENRICHED U(6.5 AND 4.4 WT.% 235U)O2 FUEL RODS IN LIGHT WATER AT DIFFERENT CORE CRITICAL DIMENSIONS	2006	11
MIX-MET-FAST-003	VNIITF	SPHERE OF PLUTONIUM SURROUNDED BY HIGHLY ENRICHED URANIUM	1997	1
MIX-MET-FAST-004	VNIITF	SPHERES OF PLUTONIUM SURROUNDED BY HIGHLY ENRICHED URANIUM AND REFLECTED BY BERYLLIUM OR BERYLLIUM OXIDE	1997	2
MIX-MET-FAST-005	VNIITF	SPHERE OF PLUTONIUM SURROUNDED BY HIGHLY ENRICHED URANIUM AND REFLECTED BY ALUMINIUM	1997	1
MIX-MET-FAST-006	IPPE	BFS-61 ASSEMBLIES: CRITICAL EXPERIMENTS OF MIXED PLUTONIUM, DEPLETED URANIUM, GRAPHITE AND LEAD WITH DIFFERENT REFLECTORS	2010	3
MIX-MET-FAST-009	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(δ, 98%) WITH A 0.75-CM EXTERNAL SHELL OF 235U(90%)	1998	1
MIX-MET-FAST-010	VNIIEF	SPHERICAL ASSEMBLY OF 239PU(δ, 98%) WITH A 2.89-CM EXTERNAL SHELL OF 235U(90%)	1998	1
MIX-MET-FAST-015	IPPE	K-INFINITY EXPERIMENTS FOR 238U IN FAST NEUTRON SPECTRA: MEASUREMENTS WITH ENRICHED URANIUM OR PLUTONIUM MIXED WITH DEPLETED URANIUM (BFS-35, BFS-33, BFS-38, BFS-31, AND BFS-42 ASSEMBLIES)	2004	11
MIX-MET-MIXED-001	VNIITF	HETEROGENEOUS CYLINDER OF PLUTONIUM, HIGHLY ENRICHED URANIUM, AND POLYETHYLENE	1998	1
MIX-MISC-FAST-001	IPPE	K-INFINITY EXPERIMENTS FOR 238U IN FAST NEUTRON SPECTRA: MEASUREMENTS WITH ENRICHED URANIUM OR PLUTONIUM MIXED WITH DEPLETED URANIUM (BFS-35, BFS-33, BFS-38, BFS-31, AND BFS-42 ASSEMBLIES)	2004	11
MIX-MISC-FAST-002	IPPE	BFS-49 ASSEMBLIES: CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF PLUTONIUM, DEPLETED-URANIUM DIOXIDE, AND POLYETHYLENE	2006	2
MIX-MISC-FAST-003	IPPE	BFS-97, -99, -101 ASSEMBLIES: CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF PLUTONIUM, DEPLETED-URANIUM DIOXIDE, AND POLYETHYLENE	2006	11
MIX-MISC-FAST-004	IPPE	BFS-97, -99 ASSEMBLIES, PART II: CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF PLUTONIUM, DEPLETED-URANIUM DIOXIDE, AND POLYETHYLENE	2011	5
MIX-MISC-MIXED-001	IPPE	BFS-97, -99, -101 ASSEMBLIES: CRITICAL EXPERIMENTS WITH HETEROGENEOUS COMPOSITIONS OF PLUTONIUM, DEPLETED-URANIUM DIOXIDE, AND POLYETHYLENE	2006	11

Serbia

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
HEU-COMP-THERM-017	Vinča	RB REACTOR: LATTICES OF 80%-ENRICHED URANIUM ELEMENTS IN HEAVY WATER	2000	9
LEU-MET-THERM-001	Vinča	RB REACTOR: NATURAL-URANIUM RODS IN HEAVY WATER	1999	1
LEU-MET-THERM-002	Vinča	RB REACTOR: LATTICES OF 2%-ENRICHED URANIUM ELEMENTS IN HEAVY WATER	1999	12
LEU-MET-THERM-015	Vinča	RB REACTOR: FUEL ASSEMBLIES SUBSTITUTION CRITICALITY EXPERIMENTS IN LATTICES OF 2%-ENRICHED URANIUM IN HEAVY WATER	2006	22

Slovenia

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
IEU-COMP-THERM-003	IJS	TRIGA MARK II REACTOR: U(20) – ZIRCONIUM HYDRIDE FUEL RODS IN WATER WITH GRAPHITE REFLECTOR	1999	2

Spain

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
HEU-MET-FAST-062	CIEMAT	FIRST CRITICALITY OF CORAL-I REACTOR, A 90%-ENRICHED URANIUM CYLINDER REFLECTED BY NATURAL URANIUM, BOTH METAL	2001	1

Sweden

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
IEU-MET-FAST-020	Studsvik	THE FR0 SERIES 1: COPPER-REFLECTED “CYLINDRICAL” URANIUM (20 % 235U) METAL	2008	9
IEU-MET-FAST-021	Studsvik	THE FR0 SERIES 4: 20%-ENRICHED “CYLINDRICAL” URANIUM METAL REFLECTED BY NATURAL URANIUM	2009	1
IEU-MET-FAST-022	Studsvik	THE FR0 EXPERIMENTS WITH DILUTED 20%-ENRICHED "CYLINDRICAL" URANIUM METAL REFLECTED BY COPPER	2011	7
IEU-MET-INTER-001	Studsvik	THE FR0 EXPERIMENTS WITH DILUTED 20%-ENRICHED "CYLINDRICAL" URANIUM METAL REFLECTED BY COPPER	2011	7

United Kingdom

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
PU-COMP-INTER-001	Winfrith	K-INFINITY EXPERIMENTS IN INTERMEDIATE NEUTRON SPECTRA FOR 239PU	1999	1
HEU-COMP-INTER-004	Winfrith	k-infinity EXPERIMENTS IN INTERMEDIATE NEUTRON SPECTRA FOR 235U	1999	1
IEU-MET-FAST-011	Winfrith	K-INFINITY MEASUREMENTS IN ZEBRA CORE 8	1997	7
IEU-MET-FAST-019	Aldermaston	45.5% 235U PSEUDO-CYLINDRICAL METAL SLABS: BARE ASSEMBLIES	2007	2
IEU-SOL-THERM-002	Dounreay	BARE AND WATER-REFLECTED SPHERES AND HEMISPHERES OF AQUEOUS URANYL FLUORIDE SOLUTIONS (30.45% 235U)	2010	13
IEU-SOL-THERM-003	Dounreay	BARE AND WATER REFLECTED CYLINDERS OF AQUEOUS URANYL FLUORIDE SOLUTIONS (30.3% 235U)	2011	46
IEU-COMP-INTER-006	Aldermaston	SINGLE CORES OF 30.14% 235U ENRICHED UO2 / WAX MIXTURES – BARE AND WITH SINGLE REFLECTOR MATERIALS	2012	33
IEU-COMP-THERM-015	Aldermaston	SINGLE CORES OF 30.14% 235U ENRICHED UO2 / WAX MIXTURES – BARE AND WITH SINGLE REFLECTOR MATERIALS	2012	33
IEU-COMP-THERM-016	Aldermaston	SINGLE CORES OF 30.14% 235U ENRICHED UO2 / WAX MIXTURES WITH COMPOSITE REFLECTORS	2012	45
IEU-COMP-MIXED-004	Aldermaston	SINGLE CORES OF 30.14% 235U ENRICHED UO2 / WAX MIXTURES – BARE AND WITH SINGLE REFLECTOR MATERIALS	2012	33
LEU-COMP-THERM-018	Winfrith	LIGHT WATER MODERATED AND REFLECTED LOW ENRICHED URANIUM DIOXIDE (7 WT.%) ROD LATTICE	1996	1
LEU-COMP-THERM-047	Winfrith	FUEL TRANSPORT FLASK CRITICAL BENCHMARK EXPERIMENTS WITH LOW-ENRICHED URANIUM DIOXIDE FUEL	2000	3
LEU-COMP-THERM-048	Winfrith	LIGHT WATER MODERATED AND REFLECTED LOW-ENRICHED (3 WT.% 235U) URANIUM DIOXIDE ROD LATTICES	2001	5
LEU-COMP-THERM-055	Winfrith	LIGHT-WATER MODERATED AND REFLECTED LOW-ENRICHED URANIUM (3 wt.% 235U) DIOXIDE ROD LATTICES	2002	2
LEU-COMP-THERM-063	Winfrith	LIGHT-WATER MODERATED AND REFLECTED LOW-ENRICHED URANIUM (3 wt.% 235U) DIOXIDE ROD LATTICES WITH DISCRETE POISON-ROD ARRAYS	2003	12
LEU-COMP-THERM-076	Winfrith	LIGHT WATER MODERATED AND REFLECTED LOW ENRICHED URANIUM (3 WT.% 235U) DIOXIDE ROD LATTICES WITH EX-CORE DETECTOR FEATURE	2004	7
MIX-MET-FAST-008	Winfrith	K-INFINITY MEASUREMENTS IN ZEBRA CORE 8	1997	7
MIX-MET-INTER-001	Winfrith	K-INFINITY MEASUREMENTS IN ZEBRA CORE 8	1997	7
MIX-SOL-THERM-003	Aldermaston	WATER/POLYETHYLENE REFLECTED CYLINDERS OF PLUTONIUM/NATURAL URANIUM NITRATE	1995	10
SUB-LEU-COMP-THERM-001	Winfrith	FUEL-TRANSPORT-FLASK SUBCRITICAL EXPERIMENTS WITH LOW-ENRICHED URANIUM (3 wt.% 235U) DIOXIDE FUEL	2000	15

United States

Evaluation ID	Laboratory	Evaluation Title	Year	Cases
PU-MET-FAST-001	LANL	BARE SPHERE OF PLUTONIUM-239 METAL (4.5 at.%. 240Pu, 1.02 wt.% Ga)	1995	4
PU-MET-FAST-002	LANL	240 Pu JEZEBEL: BARE SPHERE OF PLUTONIUM-239 METAL (20.1 at.% 240 Pu, 1.01 wt.% Ga)	1995	1
PU-MET-FAST-003	LLNL	UNMODERATED PLUTONIUM METAL BUTTON ARRAY	1995	5
PU-MET-FAST-004	LLNL	UNMODERATED PLUTONIUM METAL CYLINDER ARRAY - PHASE II	1995	9
PU-MET-FAST-005	LANL	BENCHMARK CRITICAL EXPERIMENT OF A PLUTONIUM SPHERE REFLECTED BY TUNGSTEN	1995	1
PU-MET-FAST-006	LANL	PLUTONIUM SPHERE REFLECTED BY NORMAL URANIUM USING FLATTOP	1997	1
PU-MET-FAST-008	LANL	BENCHMARK CRITICAL EXPERIMENT OF A THORIUM REFLECTED PLUTONIUM SPHERE	1995	1
PU-MET-FAST-009	LANL	BENCHMARK CRITICAL EXPERIMENT OF A PLUTONIUM SPHERE REFLECTED BY ALUMINUM	1996	1
PU-MET-FAST-010	LANL	BENCHMARK CRITICAL EXPERIMENT OF A DELTA-PHASE PLUTONIUM SPHERE REFLECTED BY NORMAL URANIUM	1995	1
PU-MET-FAST-011	LANL	BENCHMARK CRITICAL EXPERIMENT OF A WATER REFLECTED ALPHA-PHASE PLUTONIUM SPHERE	1995	1
PU-MET-FAST-016	Rocky Flats	FLOODED 3x3x3 ARRAYS OF 3-KG PLUTONIUM METAL CYLINDERS - PHASE I	1997	6
PU-MET-FAST-017	LLNL	MODERATED PLUTONIUM METAL CYLINDERS ARRAY - PHASE II	1995	6
PU-MET-FAST-018	LANL	BENCHMARK CRITICAL EXPERIMENT OF A DELTA-PHASE PLUTONIUM SPHERE REFLECTED BY BERYLLIUM	1996	1
PU-MET-FAST-033	ANL-W	ZPPR-21 PHASE A: A CYLINDRICAL ASSEMBLY OF PU METAL REFLECTED BY GRAPHITE	2001	1
PU-MET-FAST-037	Rocky Flats	FLOODED 2x2xN ARRAYS OF 3-KG PLUTONIUM METAL CYLINDERS - PHASE 2	1998	23
PU-MET-FAST-038	LANL	PLUTONIUM SPHERE REFLECTED BY BERYLLIUM	2007	1
PU-MET-FAST-042	Rocky Flats	PLUTONIUM HEMISPHERES REFLECTED BY STEEL AND OIL	2008	15
PU-MET-FAST-044	LANL	Plutonium (5.1 wt.% 240Pu) Metal Sphere with Beryllium, Graphite, Aluminum, Iron, and Molybdenum Tampers and Polyethylene Reflectors	2007	5
PU-MET-FAST-045	LANL	CRITICAL EXPERIMENTS PERFORMED FOR LAMPRE, THE LOS ALAMOS MOLTEN PLUTONIUM REACTOR	2002	7
PU-MET-INTER-002	ANL	ZPR-6 ASSEMBLY 10: A CYLINDRICAL PLUTONIUM/CARBON/STAINLESS STEEL ASSEMBLY WITH STAINLESS STEEL AND IRON REFLECTORS	2002	1
PU-MET-INTER-003	ANL-W	ZPR-3 ASSEMBLY 58: A CYLINDRICAL ASSEMBLY OF PLUTONIUM METAL AND GRAPHITE WITH A THICK DEPLETED URANIUM REFLECTOR	2014	1
PU-MET-INTER-004	ANL-W	ZPR-3 ASSEMBLY 59: A CYLINDRICAL ASSEMBLY OF PLUTONIUM METAL AND GRAPHITE WITH A THICK LEAD REFLECTOR	2014	1
PU-MET-MIXED-003	LANL	TEX PLUTONIUM TANTALUM ASSEMBLIES: PLUTONIUM/ALUMINUM METAL ALLOY PLATES WITH VARYING THICKNESSES OF POLYETHYLENE MODERATOR, INTERSTITIAL TANTALUM, AND A THIN POLYETHYLENE REFLECTOR	2021	5
PU-SOL-THERM-001	PNL	WATER-REFLECTED 11.5-INCH DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1995	6
PU-SOL-THERM-002	Hanford (P-11)	WATER-REFLECTED 12-INCH DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1995	7
PU-SOL-THERM-003	Hanford (P-11)	WATER-REFLECTED 13-INCH DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1995	9
PU-SOL-THERM-004	Hanford (P-11)	WATER-REFLECTED 14-INCH DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS, 0.54% TO 3.43% 240Pu	1995	13
PU-SOL-THERM-005	Hanford (P-11)	WATER-REFLECTED 14-INCH DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS, 4.05% AND 4.40% Pu240	1995	11
PU-SOL-THERM-006	Hanford (P-11)	WATER-REFLECTED 15-INCH DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1995	3
PU-SOL-THERM-007	PNL	WATER-REFLECTED 11.5-INCH-DIAMETER SPHERES PARTLY FILLED WITH PLUTONIUM NITRATE SOLUTIONS	1996	11
PU-SOL-THERM-008	PNL	CONCRETE-REFLECTED 14-INCH-DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1999	15
PU-SOL-THERM-009	PNL	UNREFLECTED 48-INCH-DIAMETER SPHERE OF PLUTONIUM NITRATE SOLUTION	1996	3
PU-SOL-THERM-010	Hanford (P-11)	WATER-REFLECTED 9-, 10-, 11-, AND 12-INCH-DIAMETER CYLINDERS OF PLUTONIUM NITRATE SOLUTIONS	1996	35
PU-SOL-THERM-011	Hanford (P-11)	BARE 16- AND 18-INCH-DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1996	13
PU-SOL-THERM-018	PNL	WATER-REFLECTED 24-INCH DIAMETER CYLINDER OF PLUTONIUM (42.9% 240Pu) NITRATE SOLUTION	2006	9
PU-SOL-THERM-020	PNL	WATER-REFLECTED AND WATER-CADMIUM-REFLECTED 14-INCH DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1997	43
PU-SOL-THERM-021	PNL	WATER-REFLECTED AND BARE 15.2-INCH-DIAMETER SPHERES OF PLUTONIUM NITRATE SOLUTIONS	1998	101
PU-SOL-THERM-024	PNL	SLABS OF PLUTONIUM NITRATE SOLUTIONS REFLECTED BY 1-INCH-THICK PLEXIGLAS	1998	23
PU-SOL-THERM-025	PNL	WATER-REFLECTED SLABS OF PLUTONIUM NITRATE SOLUTIONS	1998	44
PU-SOL-THERM-026	PNL	UNREFLECTED SLABS OF PLUTONIUM NITRATE SOLUTIONS	1999	21
PU-SOL-THERM-034	PNL	PLUTONIUM (8.3 wt.% 240Pu) NITRATE SOLUTION WITH GADOLINIUM IN WATER-REFLECTED 24-INCH DIAMETER CYLINDER	2007	15
PU-COMP-FAST-001	PNL	UNREFLECTED SLABS OF POLYSTYRENE-MODERATED PLUTONIUM OXIDE	1999	5
PU-COMP-FAST-002	PNL	PLEXIGLAS REFLECTED SLABS OF POLYSTYRENE-MODERATED PLUTONIUM OXIDE	1999	29
PU-COMP-INTER-002	PNL	UNREFLECTED SLABS OF POLYSTYRENE-MODERATED PLUTONIUM OXIDE	1999	5
PU-COMP-THERM-001	PNL	UNREFLECTED SLABS OF POLYSTYRENE-MODERATED PLUTONIUM OXIDE	1999	5
PU-COMP-THERM-002	PNL	PLEXIGLAS REFLECTED SLABS OF POLYSTYRENE-MODERATED PLUTONIUM OXIDE	1999	29
PU-COMP-MIXED-001	PNL	UNREFLECTED SLABS OF POLYSTYRENE-MODERATED PLUTONIUM OXIDE	1999	5
PU-COMP-MIXED-002	PNL	PLEXIGLAS REFLECTED SLABS OF POLYSTYRENE-MODERATED PLUTONIUM OXIDE	1999	29
HEU-MET-FAST-001	LANL	BARE, HIGHLY ENRICHED URANIUM SPHERE (GODIVA)	1995	1
HEU-MET-FAST-002	LANL	TOPSY 8-INCH-TUBALLOY-REFLECTED ORALLOY ASSEMBLIES	1995	6
HEU-MET-FAST-003	LANL	REFLECTED ORALLOY SPHERICAL ASSEMBLIES	1995	12
HEU-MET-FAST-004	LANL	WATER-REFLECTED, HIGHLY ENRICHED URANIUM SPHERE	1995	1
HEU-MET-FAST-006	LANL	LATTICES OF ORALLOY CUBES IN WATER	1995	7
HEU-MET-FAST-007	ORNL	URANIUM METAL SLABS MODERATED WITH POLYETHYLENE, PLEXIGLAS, AND TEFLON	1995	43
HEU-MET-FAST-023	ORNL	TINKERTOY: UNMODERATED URANIUM METAL (93.2) ARRAYS WITH CYLINDERS OF 10.5 KG MASS	1996	24
HEU-MET-FAST-026	ORNL	TINKERTOY 2: BARE AND PARAFFIN-REFLECTED URANIUM (93.2) METAL ARRAYS WITH 15, 20 AND 25-KG CYLINDERS	1997	32
HEU-MET-FAST-028	LANL	URANIUM-235 SPHERE REFLECTED BY NORMAL URANIUM USING FLATTOP	1997	1
HEU-MET-FAST-032	LANL	235U(94%) SPHERES SURROUNDED BY NATURAL-URANIUM REFLECTORS	1998	4
HEU-MET-FAST-041	LANL	235U(94%) SPHERES SURROUNDED BY BERYLLIUM OR GRAPHITE REFLECTORS	1999	6
HEU-MET-FAST-047	LANL	NIOBIUM - 1wt.% ZIRCONIUM MODERATED BY POLYETHYLENE AND FUELED WITH HIGHLY ENRICHED URANIUM	2006	1
HEU-MET-FAST-048	Rocky Flats	OIL-REFLECTED SPHERES AND HEMISPHERES OF HIGHLY ENRICHED URANIUM (93.1% 235U) METAL WITH OIL OR STEEL MODERATOR	2001	17
HEU-MET-FAST-051	ORNL	URANIUM (93.2) METAL CYLINDERS (7-INCH, 9-INCH, 11-INCH, 13-INCH, AND 15-INCH DIAMETER) AND TWO 11-INCH-DIAMETER INTERACTING URANIUM (93.2) METAL CYLINDERS	2002	18
HEU-MET-FAST-053	ORNL	POLYETHYLENE-REFLECTED ARRAYS OF HEU METAL CYLINDERS SEPARATED BY PLYWOOD, CELOTEX, FOAMGLAS, OR BORATED PLASTIC FOAM	2009	7
HEU-MET-FAST-055	ANL-W	ZPR-3 ASSEMBLY 23: A CYLINDRICAL ASSEMBLY OF U METAL (93% 235U) AND ALUMINUM REFLECTED BY DEPLETED-URANIUM	2000	1
HEU-MET-FAST-056	ORNL	POLYETHYLENE-REFLECTED ARRAYS OF HEU(93.2) METAL UNITS SEPARATED BY VERMICULITE	2010	1
HEU-MET-FAST-057	LLNL	HIGHLY ENRICHED URANIUM METAL SPHERES AND CYLINDERS REFLECTED BY LEAD	2004	6
HEU-MET-FAST-058	LLNL	HIGHLY ENRICHED URANIUM METAL SPHERES WITH BERYLLIUM REFLECTORS	2003	5
HEU-MET-FAST-059	ORNL	Oralloy (93.15 235U) Metal Annuli with Beryllium Core	2010	2
HEU-MET-FAST-060	ANL	ZPR-9 ASSEMBLY 4: A CYLINDRICAL ASSEMBLY OF U METAL (93% 235U) AND TUNGSTEN WITH ALUMINUM REFLECTORS	2002	1
HEU-MET-FAST-061	ANL-W	ZPPR-21 PHASE F: A CYLINDRICAL ASSEMBLY OF U METAL REFLECTED BY GRAPHITE	2001	1
HEU-MET-FAST-063	LANL	CYLINDRICAL EXPERIMENTS USING HEU PLATES REFLECTED BY LITHIUM DEUTERIDE	2004	2
HEU-MET-FAST-066	LLNL	METAL SPHERICAL SHELLS OF HIGHLY ENRICHED URANIUM MODERATED AND REFLECTED BY BERYLLIUM	2005	9
HEU-MET-FAST-067	ANL	ZPR-9 ASSEMBLIES 5 AND 6: HEU (93% 235U) CYLINDRICAL CORES WITH TUNGSTEN, GRAPHITE, AND ALUMINUM DILUENTS WITH A DENSE ALUMINUM REFLECTOR	2003	2
HEU-MET-FAST-069	ORNL	Oralloy (93.2 235U) Metal Cylinder with Beryllium Top Reflector	2010	1
HEU-MET-FAST-070	ANL	ZPR-9 ASSEMBLIES 7, 8 AND 9: CYLINDRICAL CORES WITH HEU (93% 235U), TUNGSTEN, AND ALUMINUM OR ALUMINUM OXIDE WITH A DENSE ALUMINUM, ALUMINUM OXIDE, OR BERYLLIUM OXIDE REFLECTOR	2004	3
HEU-MET-FAST-071	ORNL	URANIUM (93.14) METAL ANNULI WITH ONE- AND TWO-INCH GRAPHITE REFLECTORS	2004	27
HEU-MET-FAST-072	LANL	ZEUS: FAST-SPECTRUM CRITICAL ASSEMBLIES WITH AN IRON - HEU CORE SURROUNDED BY A COPPER REFLECTOR	2004	3
HEU-MET-FAST-073	LANL	THE UNMODERATED ZEUS EXPERIMENT: A CYLINDRICAL HEU CORE SURROUNDED BY A COPPER REFLECTOR	2005	1
HEU-MET-FAST-074	ORNL	ORALLOY (93.2 235U) BARE METAL ANNULI AND DISKS	2015	4
HEU-MET-FAST-075	ANL-W	ZPPR-20 PHASE C: A CYLINDRICAL ASSEMBLY OF U METAL REFLECTED BY BERYLLIUM OXIDE	2005	1
HEU-MET-FAST-076	ORNL	URANIUM (93.14 235U) METAL ANNULI AND CYLINDERS WITH THICK POLYETHYLENE REFLECTORS AND/OR INTERNAL POLYETHYLENE MODERATOR	2006	25
HEU-MET-FAST-077	ORNL	EXPERIMENTS WITH HEU (93.14 wt. %) METAL ANNULI WITH INTERNAL GRAPHITE CYLINDER	2015	3
HEU-MET-FAST-078	LANL	HEU METAL CYLINDERS, PARTIALLY REFLECTED BY WATER, POLYETHYLENE, LUCITE, AND PARAFFIN	2006	44
HEU-MET-FAST-081	ORNL	GROTESQUE: COMPLEX GEOMETRIC ARRANGEMENT OF UNREFLECTED HEU (93.15) METAL PIECES	2011	1
HEU-MET-FAST-083	ORNL	COMPLEX GEOMETRY BARE ORALLOY (93.15 235U) METAL ANNULI EXPERIMENTS	2016	3
HEU-MET-FAST-084	LANL	HEU METAL CYLINDERS WITH MAGNESIUM, TITANIUM, ALUMINUM, GRAPHITE, MILD STEEL, NICKEL, COPPER, COBALT, MOLYBDENUM, NATURAL URANIUM, TUNGSTEN, BERYLLIUM, ALUMINUM OXIDE, MOLYBDENUM CARBIDE, AND POLYETHYLENE REFLECTORS	2007	32
HEU-MET-FAST-085	LANL	HIGHLY ENRICHED URANIUM METAL SPHERES SURROUNDED BY COPPER, CAST IRON, NICKEL, NICKEL-COPPER-ZINC ALLOY, THORIUM, TUNGSTEN ALLOY, OR ZINC REFLECTORS	2007	13
HEU-MET-FAST-086	LANL	GODIVA-IV DELAYED-CRITICAL AND STATIC PROMPT SUPERCRITICAL EXPERIMENTS	2007	5
HEU-MET-FAST-096	ORNL	STATIC CRITICAL EXPERIMENTS FOR THE SORGENTE RAPIDA (SORA) REACTOR MOCKUP	2016	15
HEU-MET-FAST-099	ORNL	FAST NEUTRON SPECTRUM POTASSIUM WORTH FOR SPACE POWER REACTOR DESIGN VALIDATION	2015	2
HEU-MET-FAST-100	ORNL	ORSPHERE: CRITICAL, BARE, HEU(93.2)-METAL SPHERE	2013	2
HEU-MET-FAST-101	LANL	KRUSTY: BERYLLIUM-OXIDE AND STAINLESS-STEEL REFLECTED CYLINDER OF HEU METAL	2021	5
HEU-MET-INTER-001	ANL	THE URANIUM/IRON BENCHMARK ASSEMBLY: A 235U(93%)/IRON CYLINDER REFLECTED BY STAINLESS STEEL	1998	1
HEU-MET-INTER-006	LANL	THE INITIAL SET OF ZEUS EXPERIMENTS: INTERMEDIATE-SPECTRUM CRITICAL ASSEMBLIES WITH A GRAPHITE-HEU CORE SURROUNDED BY A COPPER REFLECTOR	2000	4
HEU-MET-INTER-007	ORNL	URANIUM METAL SLABS MODERATED WITH POLYETHYLENE, PLEXIGLAS, AND TEFLON	1995	43
HEU-MET-INTER-009	LLNL	‘SPADE’ ASSEMBLIES PART II: HIGHLY ENRICHED URANIUM METAL FOILS MODERATED BY BERYLLIUM OXIDE	2005	2
HEU-MET-INTER-010	LLNL	HIGHLY ENRICHED URANIUM METAL MODERATED BY BERYLLIUM OXIDE	2004	15
HEU-MET-THERM-001	LANL	POLYETHYLENE REFLECTED AND MODERATED HIGHLY ENRICHED URANIUM SYSTEM WITH SILICON	2002	1
HEU-MET-THERM-003	LANL	LATTICES OF ORALLOY CUBES IN WATER	1995	7
HEU-MET-THERM-004	LANL	ONE DIMENSIONAL ARRAY OF HIGHLY ENRICHED URANIUM, MODERATED AND REFLECTED BY LUCITE	2021	2
HEU-MET-THERM-006	ORNL	SPERT-D ALUMINUM-CLAD PLATE-TYPE FUEL IN WATER, DILUTE URANYL NITRATE, OR BORATED URANYL NITRATE	1995	25
HEU-MET-THERM-008	LANL	POLYETHYLENE REFLECTED AND MODERATED HIGHLY ENRICHED URANIUM SYSTEM WITH ALUMINUM	2002	1
HEU-MET-THERM-009	LANL	POLYETHYLENE REFLECTED AND MODERATED HIGHLY ENRICHED URANIUM SYSTEM WITH MAGNESIUM OXIDE	2002	1
HEU-MET-THERM-010	LANL	POLYETHYLENE REFLECTED AND MODERATED HIGHLY ENRICHED URANIUM SYSTEMS WITH GADOLINIUM	2002	2
HEU-MET-THERM-012	LANL	2 x 2 x 26 ARRAY OF HIGHLY ENRICHED URANIUM WITH ALUMINUM, MODERATED AND REFLECTED BY POLYETHYLENE	2004	1
HEU-MET-THERM-013	LANL	POLYETHYLENE REFLECTED AND MODERATED HIGHLY ENRICHED URANIUM SYSTEMS WITH IRON	2003	2
HEU-MET-THERM-014	LANL	2 x 2 x 23 ARRAY OF HIGHLY ENRICHED URANIUM WITH SILICON DIOXIDE, MODERATED AND REFLECTED BY POLYETHYLENE	2003	1
HEU-MET-THERM-015	LANL	2 x 2 ARRAY OF HIGHLY ENRICHED URANIUM WITH IRON, MODERATED AND REFLECTED BY POLYETHYLENE	2005	1
HEU-MET-THERM-016	LANL	2 x 2 x 11 ARRAY OF HIGHLY ENRICHED URANIUM WITH NI-CR-MO-GD ALLOY, MODERATED AND REFLECTED BY POLYETHYLENE	2003	1
HEU-MET-THERM-018	LANL	POLYETHYLENE REFLECTED AND MODERATED HIGHLY ENRICHED URANIUM SYSTEM WITH CONCRETE	2004	1
HEU-MET-THERM-022	INL	ADVANCED TEST REACTOR: SERPENTINE ARRANGEMENT OF HIGHLY ENRICHED WATER-MODERATED URANIUM-ALUMINIDE FUEL PLATES REFLECTED BY BERYLLIUM	2005	1
HEU-MET-THERM-025	ORNL	BERYLLIUM MODERATED CRITICAL ASSEMBLIES OF HIGHLY ENRICHED URANIUM (ORNL CA-1 and CA-18)	2003	2
HEU-MET-THERM-027	LLNL	HIGHLY ENRICHED URANIUM METAL MODERATED BY BERYLLIUM OXIDE	2004	15
HEU-MET-THERM-031	LANL	2 x 2 ARRAY OF HIGHLY ENRICHED URANIUM, MODERATED AND REFLECTED BY POLYETHYLENE	2006	1
HEU-MET-THERM-032	LANL	ONE DIMENSIONAL ARRAY OF HIGHLY ENRICHED URANIUM, MODERATED AND REFLECTED BY POLYETHYLENE	2010	2
HEU-MET-THERM-033	LANL	2 x 2 POLYETHYLENE REFLECTED AND MODERATED HIGHLY ENRICHED URANIUM SYSTEM WITH RHENIUM	2010	1
HEU-MET-THERM-034	LANL	2 x 2 x 13 ARRAY OF HIGHLY ENRICHED URANIUM WITH NI-CR-MO-GD ALLOY, MODERATED AND REFLECTED BY POLYETHYLENE	2010	1
HEU-MET-THERM-035	LLNL	HIGHLY ENRICHED URANIUM METAL FOILS MODERATED BY GRAPHITE: ‘SNOOPY 134’	2006	2
HEU-MET-MIXED-009	ORNL	URANIUM METAL SLABS MODERATED WITH POLYETHYLENE, PLEXIGLAS, AND TEFLON	1995	43
HEU-MET-MIXED-010	LANL	LATTICES OF ORALLOY CUBES IN WATER	1995	7
HEU-MET-MIXED-011	Rocky Flats	OIL-REFLECTED SPHERES AND HEMISPHERES OF HIGHLY ENRICHED URANIUM (93.1% 235U) METAL WITH OIL OR STEEL MODERATOR	2001	17
HEU-MET-MIXED-012	ANL-W	ZPPR-20 PHASE D: A CYLINDRICAL ASSEMBLY OF POLYETHYLENE-MODERATED U METAL REFLECTED BY BERYLLIUM OXIDE AND POLYETHYLENE	2006	1
HEU-MET-MIXED-014	ORNL	URANIUM (93.14 235U) METAL ANNULI AND CYLINDERS WITH THICK POLYETHYLENE REFLECTORS AND/OR INTERNAL POLYETHYLENE MODERATOR	2006	25
HEU-SOL-INTER-001	LANL	REFLECTED URANYL-FLUORIDE SOLUTIONS IN HEAVY WATER	1995	6
HEU-SOL-THERM-001	Rocky Flats	MINIMALLY REFLECTED CYLINDERS OF HIGHLY ENRICHED SOLUTIONS OF URANYL NITRATE	1995	10
HEU-SOL-THERM-002	Rocky Flats	CONCRETE REFLECTED CYLINDERS OF HIGHLY ENRICHED SOLUTIONS OF URANYL NITRATE	1995	14
HEU-SOL-THERM-003	Rocky Flats	PLEXIGLAS REFLECTED CYLINDERS OF HIGHLY ENRICHED SOLUTIONS OF URANYL NITRATE	1995	19
HEU-SOL-THERM-004	LANL	REFLECTED URANYL-FLUORIDE SOLUTIONS IN HEAVY WATER	1995	6
HEU-SOL-THERM-005	ORNL	AQUEOUS SOLUTIONS OF 235U POISONED WITH PYREX GLASS PIPES	1998	27
HEU-SOL-THERM-006	LANL	EXPERIMENTS WITH BORON-POISONED HIGHLY ENRICHED URANYL NITRATE SOLUTION	1997	29
HEU-SOL-THERM-007	Rocky Flats	CONCRETE REFLECTED ARRAYS OF HIGHLY ENRICHED SOLUTIONS OF URANYL NITRATE	1995	17
HEU-SOL-THERM-008	Rocky Flats	PLEXIGLAS REFLECTED ARRAYS OF HIGHLY ENRICHED SOLUTIONS OF URANYL NITRATE	1995	14
HEU-SOL-THERM-009	ORNL	WATER-REFLECTED 6.4-LITER SPHERES OF ENRICHED URANIUM OXYFLUORIDE SOLUTIONS	1996	4
HEU-SOL-THERM-010	ORNL	WATER-REFLECTED 9.7 LITER SPHERES OF ENRICHED URANIUM OXYFLUORIDE SOLUTIONS	1996	4
HEU-SOL-THERM-011	ORNL	WATER-REFLECTED 17 LITER SPHERES OF ENRICHED URANIUM OXYFLUORIDE SOLUTIONS	1996	2
HEU-SOL-THERM-012	ORNL	WATER-REFLECTED 91-LITER SPHERE OF ENRICHED URANIUM OXYFLUORIDE SOLUTION	1996	1
HEU-SOL-THERM-013	ORNL	UNREFLECTED 174-LITER SPHERES OF ENRICHED URANIUM NITRATE SOLUTIONS	1996	4
HEU-SOL-THERM-020	LANL	UNREFLECTED CYLINDERS OF URANYL-FLUORIDE SOLUTIONS IN HEAVY WATER	1996	5
HEU-SOL-THERM-021	ORNL	BARE AND HYDROGENOUS REFLECTED ARRAYS OF HIGHLY ENRICHED SOLUTIONS OF URANYL NITRATE (1F EXPERIMENTS)	1996	34
HEU-SOL-THERM-026	Rocky Flats	HIGHLY ENRICHED URANYL NITRATE IN ANNULAR TANKS WITH CONCRETE REFLECTION: 1 × 3 LINE ARRAY OF NESTED PAIRS OF TANKS	2009	17
HEU-SOL-THERM-032	ORNL	A 48-INCH-DIAMETER UNREFLECTED SPHERE OF URANYL NITRATE (93.2 wt.% 235U) SOLUTION	1998	1
HEU-SOL-THERM-033	Rocky Flats	HIGHLY ENRICHED URANYL NITRATE IN ANNULAR TANKS WITH CONCRETE REFLECTION: FOUR NESTED TANKS	1998	28
HEU-SOL-THERM-034	ORNL	WATER-MODERATED AND -REFLECTED SLABS OF URANIUM OXYFLUORIDE	2010	5
HEU-SOL-THERM-038	LANL	WINCO SLAB TANKS: TWO INTERACTING TANKS OF HIGHLY ENRICHED URANYL NITRATE SOLUTION WITH VARIOUS ABSORBER-REFLECTOR PLATES	2002	30
HEU-SOL-THERM-040	Rocky Flats	INTERSECTING PIPE CONFIGURATIONS CONTAINING HIGHLY CONCENTRATED (453 gU/l) AND HIGHLY ENRICHED (93.17 wt.% 235U) URANYL NITRATE SOLUTION	2002	17
HEU-SOL-THERM-042	ORNL	UNREFLECTED LARGE-DIAMETER CYLINDERS OF ENRICHED URANIUM NITRATE SOLUTIONS	2001	8
HEU-SOL-THERM-043	ORNL	LARGE UNREFLECTED SPHERES OF URANIUM OXYFLUORIDE SOLUTIONS	2000	8
HEU-SOL-THERM-044	Rocky Flats	CONCRETE-REFLECTED URANYL NITRATE SOLUTION CYLINDER CONTAINING PERIODICALLY DISTRIBUTED ABSORBER RODS	2000	45
HEU-SOL-THERM-047	ORNL	INTERACTION OF UNREFLECTED ALUMINUM CYLINDERS IN A HEXAGONAL ARRAY CONTAINING URANYL FLUORIDE SOLUTION	2011	18
HEU-SOL-THERM-048	ORNL	CRITICAL PARAMETERS OF ENRICHED 235U SOLUTIONS IN REFLECTED, INTERACTING ARRAYS OF ALUMINUM CYLINDERS	2012	24
HEU-SOL-THERM-049	PNL	HIGHLY ENRICHED URANYL NITRATE SOLUTION CONTAINING CADMIUM	2004	20
HEU-SOL-THERM-050	ORNL	UNREFLECTED ALUMINUM CYLINDERS CONTAINING URANYL FLUORIDE SOLUTIONS	2005	14
HEU-COMP-FAST-001	ORNL	CRITICAL CONFIGURATION AND PHYSICS MEASUREMENTS FOR GRAPHITE REFLECTED ASSEMBLIES OF U(93.15)O2 FUEL RODS (1.27-CM PITCH)	2012	2
HEU-COMP-FAST-002	ORNL	CRITICAL CONFIGURATION AND PHYSICS MEASUREMENTS FOR GRAPHITE REFLECTED ASSEMBLIES OF U(93.15)O2 FUEL RODS (1.506-CM PITCH)	2012	1
HEU-COMP-FAST-004	ORNL	CRITICAL CONFIGURATION FOR BERYLLIUM REFLECTED ASSEMBLIES OF U(93.15)O2 FUEL RODS (1.506-CM PITCH AND 7-TUBE CLUSTERS)	2012	4
HEU-COMP-INTER-003	LANL	REFLECTED URANIUM-HYDRIDE CYLINDRICAL ASSEMBLIES	2000	7
HEU-COMP-THERM-001	ORNL	ARRAYS OF CANS OF HIGHLY ENRICHED URANIUM DIOXIDE REFLECTED BY POLYETHYLENE	1999	26
HEU-COMP-THERM-002	ORNL	GRAPHITE AND WATER MODERATED NRX-A3 AND NRX-A4 ASSEMBLIES	1998	25
HEU-COMP-THERM-010	ORNL	EBOR FUEL PINS IN WATER, BORATED WATER, OR URANYL NITRATE	1997	21
HEU-COMP-THERM-015	BAPL	LWBR SB CORE EXPERIMENTS	2003	8
HEU-COMP-THERM-018	BAPL	ETA-I: D2O MODERATED LATTICE OF UO2-THO2	2011	1
HEU-COMP-THERM-021	B&W	WATER REFLECTED AND MODERATED UNIFORM LATTICE CORES OF ALUMINUM CLAD URANIUM OXIDE AND THORIUM OXIDE WITH AND WITHOUT BORON POISON	2006	101
HEU-COMP-THERM-022	INL	SPERT III STAINLESS-STEEL-CLAD PLATE-TYPE FUEL IN WATER	2001	11
HEU-COMP-MIXED-001	ORNL	ARRAYS OF CANS OF HIGHLY ENRICHED URANIUM DIOXIDE REFLECTED BY POLYETHYLENE	1999	26
HEU-MISC-THERM-001	ORNL	SPERT-D ALUMINUM-CLAD PLATE-TYPE FUEL IN WATER, DILUTE URANYL NITRATE, OR BORATED URANYL NITRATE	1995	25
HEU-MISC-THERM-002	ORNL	EBOR FUEL PINS IN WATER, BORATED WATER, OR URANYL NITRATE	1997	21
IEU-MET-FAST-001	LANL	THE EARLY JEMIMA EXPERIMENTS: BARE CYLINDRICAL CONFIGURATIONS OF ENRICHED AND NATURAL URANIUM	1995	4
IEU-MET-FAST-002	LANL	NATURAL URANIUM REFLECTED ASSEMBLY OF ENRICHED AND NATURAL URANIUM PLATES	1996	1
IEU-MET-FAST-007	LANL	BIG TEN: A LARGE, MIXED-URANIUM-METAL CYLINDRICAL CORE WITH 10% AVERAGE 235U ENRICHMENT, SURROUNDED BY A THICK 238U REFLECTOR	1998	1
IEU-MET-FAST-010	ANL	THE U9 BENCHMARK ASSEMBLY: A CYLINDRICAL ASSEMBLY OF U METAL (9% 235U) WITH A THICK DEPLETED-URANIUM REFLECTOR	1999	1
IEU-MET-FAST-012	ANL-W	ZPR-3 ASSEMBLY 41: A CYLINDRICAL ASSEMBLY OF U METAL (16% 235U), ALUMINUM, AND STEEL, REFLECTED BY DEPLETED-URANIUM	2001	1
IEU-MET-FAST-013	ANL	ZPR-9 ASSEMBLY 1: A CYLINDRICAL ASSEMBLY OF U METAL (93% 235U) AND DEPLETED URANIUM WITH ALUMINUM REFLECTORS	2004	1
IEU-MET-FAST-014	ANL	ZPR-9 ASSEMBLIES 2 AND 3: CYLINDRICAL ASSEMBLIES OF U METAL AND TUNGSTEN WITH ALUMINUM REFLECTORS	2002	2
IEU-MET-FAST-015	ANL-W	ZPR-3 ASSEMBLY 6F: A SPHERICAL ASSEMBLY OF HIGHLY ENRICHED URANIUM, DEPLETED URANIUM, ALUMINUM AND STEEL WITH AN AVERAGE 235U ENRICHMENT OF 47 ATOM %	2010	1
IEU-MET-FAST-016	ANL-W	ZPR-3 ASSEMBLY 11: A CYLINDRICAL ASSEMBLY OF HIGHLY ENRICHED URANIUM AND DEPLETED URANIUM WITH AN AVERAGE 235U ENRICHMENT OF 12 ATOM % AND A DEPLETED URANIUM REFLECTOR	2010	1
IEU-SOL-THERM-004	LANL	Water Boiler Experiment: Beryllium Oxide-Reflected Sphere Containing Uranyl (14.7) Sulfate Solution	2004	1
IEU-SOL-THERM-005	ORNL	UNREFLECTED CRITICAL DIMENSION OF AQUEOUS SOLUTION OF U(37 %)O2F2 IN SPHERICAL GEOMETRY	2015	1
IEU-COMP-FAST-001	ANL	ZPR-6 ASSEMBLY 6A: A CYLINDRICAL ASSEMBLY WITH URANIUM OXIDE FUEL AND SODIUM WITH A THICK DEPLETED-URANIUM BLANKET	2004	1
IEU-COMP-FAST-004	ANL-W	ZPR-3 ASSEMBLY 12: A CYLINDRICAL ASSEMBLY OF HIGHLY ENRICHED URANIUM, DEPLETED URANIUM AND GRAPHITE WITH AN AVERAGE 235U ENRICHMENT OF 21 ATOM %	2010	1
IEU-COMP-INTER-003	ORNL	UNREFLECTED UF4-CF2 BLOCKS WITH 37.5% 235U	2006	14
IEU-COMP-INTER-004	ORNL	UNREFLECTED UF4-CF2 BLOCKS WITH URANIUM OF 30, 25, 18.8, and 12.5% 235U	2008	9
IEU-COMP-INTER-005	ANL	ZPR-6 ASSEMBLY 6A: A CYLINDRICAL ASSEMBLY WITH URANIUM OXIDE FUEL AND SODIUM WITH A THICK DEPLETED-URANIUM BLANKET	2004	1
IEU-COMP-THERM-001	ORNL	CRITICAL ARRAYS OF POLYETHYLENE-MODERATED U(30)F4-POLYTETRAFLUOROETHYLENE ONE-INCH CUBES	1995	29
IEU-COMP-THERM-009	INL	POWER BURST FACILITY: U(18)O2-CaO-ZrO2 FUEL RODS IN WATER	2009	2
IEU-COMP-THERM-011	ORNL	UNREFLECTED UF4-CF2 BLOCKS WITH 37.5% 235U	2006	14
IEU-COMP-THERM-013	INL	FRESH-CORE RELOAD OF THE NEUTRON RADIOGRAPHY (NRAD) REACTOR WITH URANIUM(20)-ERBIUM-ZIRCONIUM-HYDRIDE FUEL	2011	1
IEU-COMP-MIXED-001	ORNL	CRITICAL ARRAYS OF POLYETHYLENE-MODERATED U(30)F4-POLYTETRAFLUOROETHYLENE ONE-INCH CUBES	1995	29
IEU-COMP-MIXED-002	ORNL	UNREFLECTED UF4-CF2 BLOCKS WITH URANIUM OF 30, 25, 18.8, and 12.5% 235U	2008	9
IEU-COMP-MIXED-003	ORNL	UNREFLECTED UF4-CF2 BLOCKS WITH 37.5% 235U	2006	14
LEU-MET-THERM-004	ORNL	TRIANGULAR LATTICES OF 2.49 CM DIAMETER LEU (4.948) RODS IN WATER	2011	8
LEU-MET-THERM-007	ORNL	WATER-MODERATED AND WATER-REFLECTED 0.30 IN. DIAMETER U(4.95) METAL RODS IN SQUARE-PITCHED ARRAYS	2010	6
LEU-SOL-THERM-001	LANL	UNREFLECTED UO2F2+H2O CYLINDRICAL ASSEMBLY SHEBA-II	1997	1
LEU-SOL-THERM-002	ORNL	174 LITER SPHERES OF LOW ENRICHED (4.9%) URANIUM OXYFLUORIDE SOLUTIONS	1997	3
LEU-COMP-FAST-001	Rocky Flats	PLEXIGLAS-REFLECTED, CONCRETE-REFLECTED, OR THIN STEEL-REFLECTED U(4.46)3O8 WITH H/U=0.77 AND HEU DRIVERS	2004	10
LEU-COMP-THERM-001	PNL	WATER-MODERATED U(2.35)O2 FUEL RODS IN 2.032-CM SQUARE-PITCHED ARRAYS	1995	8
LEU-COMP-THERM-002	PNL	WATER-MODERATED U(4.31)O2 FUEL RODS IN 2.54-CM SQUARE-PITCHED ARRAYS	1995	5
LEU-COMP-THERM-003	PNL	WATER-MODERATED U(2.35)O2 FUEL RODS IN 1.684-CM SQUARE-PITCHED ARRAYS (GADOLINIUM WATER IMPURITY)	1995	23
LEU-COMP-THERM-004	PNL	WATER-MODERATED U(4.31)O2 FUEL RODS IN 1.892-CM SQUARE-PITCHED ARRAYS (GADOLINIUM WATER IMPURITY)	1995	20
LEU-COMP-THERM-005	PNL	CRITICAL EXPERIMENTS WITH LOW-ENRICHED URANIUM DIOXIDE FUEL RODS IN WATER CONTAINING DISSOLVED GADOLINIUM	2000	16
LEU-COMP-THERM-008	B&W	CRITICAL LATTICES OF UO2 FUEL RODS AND PERTURBING RODS IN BORATED WATER	1996	17
LEU-COMP-THERM-009	PNL	WATER-MODERATED RECTANGULAR CLUSTERS OF U(4.31)O2 FUEL RODS (2.54-CM PITCH) SEPARATED BY STEEL, BORAL, COPPER, CADMIUM, ALUMINUM, OR ZIRCALOY-4 PLATES	1999	27
LEU-COMP-THERM-010	PNL	WATER-MODERATED U(4.31)O2 FUEL RODS REFLECTED BY TWO LEAD, URANIUM, OR STEEL WALLS	1996	30
LEU-COMP-THERM-011	B&W	CRITICAL EXPERIMENTS SUPPORTING CLOSE PROXIMITY WATER STORAGE OF POWER REACTOR FUEL (PART I - ABSORBER RODS)	2001	15
LEU-COMP-THERM-012	PNL	WATER-MODERATED RECTANGULAR CLUSTERS OF U(2.35)O2 FUEL RODS(1.684-CM PITCH) SEPARATED BY STEEL, BORAL, BOROFLEX, CADMIUM,OR COPPER PLATES (GADOLINIUM WATER IMPURITY)	1999	10
LEU-COMP-THERM-013	PNL	WATER-MODERATED RECTANGULAR CLUSTERS OF U(4.31)O2 FUEL RODS (1.892-CM PITCH) SEPARATED BY STEEL, BORAL, BOROFLEX, CADMIUM, OR COPPER PLATES, WITH STEEL REFLECTING WALLS	2001	7
LEU-COMP-THERM-014	PNL	WATER-REFLECTED ARRAYS OF U(4.31)O2 FUEL RODS (1.890-CM AND 1.715-CM SQUARE PITCH) IN BORATED WATER	2002	9
LEU-COMP-THERM-016	PNL	WATER-MODERATED RECTANGULAR CLUSTERS OF U(2.35)O2 FUEL RODS (2.032-CM PITCH) SEPARATED BY STEEL, BORAL, COPPER, CADMIUM, ALUMINUM, OR ZIRCALOY-4 PLATES	1998	32
LEU-COMP-THERM-017	PNL	WATER-MODERATED U(2.35)O2 FUEL RODS REFLECTED BY TWO LEAD, URANIUM, OR STEEL WALLS	1996	29
LEU-COMP-THERM-028	PNL	WATER-MODERATED U(4.31)O2 FUEL RODS IN TRIANGULAR LATTICES WITH BORON, CADMIUM AND GADOLINIUM AS SOLUBLE POISONS	2008	20
LEU-COMP-THERM-033	ORNL	REFLECTED AND UNREFLECTED ASSEMBLIES OF 2 AND 3%-ENRICHED URANIUM FLUORIDE IN PARAFFIN	2001	52
LEU-COMP-THERM-042	PNL	WATER-MODERATED RECTANGULAR CLUSTERS OF U(2.35)O2 FUEL RODS (1.684-CM PITCH) SEPARATED BY STEEL, BORAL, BOROFLEX, CADMIUM, OR COPPER PLATES, WITH STEEL REFLECTING WALLS	1999	7
LEU-COMP-THERM-045	Rocky Flats	PLEXIGLAS OR CONCRETE-REFLECTED U(4.46)3O8 WITH H/U=0.77 AND INTERSTITIAL MODERATION	2003	21
LEU-COMP-THERM-051	B&W	CRITICAL EXPERIMENTS SUPPORTING CLOSE PROXIMITY WATER STORAGE OF POWER REACTOR FUEL (PART II - ISOLATING PLATES)	2001	19
LEU-COMP-THERM-056	INL	CRITICAL EXPERIMENT WITH BORAX-V BOILING WATER REACTOR TYPE FUEL ASSEMBLIES	2004	1
LEU-COMP-THERM-066	Rocky Flats	PLEXIGLAS-REFLECTED, CONCRETE-REFLECTED, OR THIN STEEL-REFLECTED U(4.46)3O8 WITH H/U=0.77 AND HEU DRIVERS	2004	10
LEU-COMP-THERM-068	Rocky Flats	PLEXIGLAS-REFLECTED, CONCRETE-REFLECTED, OR THIN STEEL-REFLECTED U(4.48)3O8 WITH H/U=1.25 OR H/U=2.03 AND HEU DRIVERS	2005	17
LEU-COMP-THERM-069	Rocky Flats	PLEXIGLAS-REFLECTED U(4.48)3O8 WITH H/U=1.25 OR H/U=2.03 AND INTERSTITIAL MODERATION	2005	5
LEU-COMP-THERM-078	SNL	WATER-MODERATED SQUARE-PITCHED U(6.90)O2 FUEL ROD LATTICES WITH 0.52 FUEL-TO-WATER VOLUME RATIO (0.855 CM PITCH)	2013	15
LEU-COMP-THERM-079	SNL	WATER-MODERATED U(4.31)O2 FUEL ROD LATTICES CONTAINING RHODIUM FOILS	2005	10
LEU-COMP-THERM-080	SNL	WATER-MODERATED SQUARE-PITCHED U(6.90)O2 FUEL ROD LATTICES WITH 0.67 FUEL TO WATER VOLUME RATIO	2012	11
LEU-COMP-THERM-096	SNL	PARTIALLY-REFLECTED WATER-MODERATED SQUARE-PITCHED U(6.90)O2 FUEL ROD LATTICES WITH 0.67 FUEL-TO-WATER RATIO (0.800 CM PITCH)	2015	19
LEU-COMP-THERM-097	SNL	TITANIUM AND/OR ALUMINUM ROD-REPLACEMENT EXPERIMENTS IN FULLY-REFLECTED WATER-MODERATED SQUARE-PITCHED U(6.90)O2 FUEL ROD LATTICES WITH 0.67 FUELTO-WATER RATIO (0.800 CM PITCH)	2016	24
LEU-COMP-THERM-102	SNL	PITCH VARIATION EXPERIMENTS IN WATER-MODERATED SQUARE-PITCHED U(6.90)O2 FUEL ROD LATTICES WITH FUEL TO WATER VOLUME RATIOS SPANNING 0.08 TO 0.67	2021	27
LEU-COMP-MIXED-001	Rocky Flats	PLEXIGLAS-REFLECTED, CONCRETE-REFLECTED, OR THIN STEEL-REFLECTED U(4.46)3O8 WITH H/U=0.77 AND HEU DRIVERS	2004	10
LEU-COMP-MIXED-002	Rocky Flats	PLEXIGLAS-REFLECTED, CONCRETE-REFLECTED, OR THIN STEEL-REFLECTED U(4.48)3O8 WITH H/U=1.25 OR H/U=2.03 AND HEU DRIVERS	2005	17
U233-MET-FAST-001	LANL	233U JEZEBEL: A BARE SPHERE OF URANIUM-233 METAL	1995	1
U233-MET-FAST-002	LANL	BENCHMARK CRITICAL EXPERIMENTS OF URANIUM-233 SPHERES SURROUNDED BY URANIUM-235	1995	2
U233-MET-FAST-003	LANL	BENCHMARK CRITICAL EXPERIMENTS OF HIGHLY ENRICHED URANIUM-233 SPHERES REFLECTED BY NORMAL URANIUM	1995	2
U233-MET-FAST-004	LANL	BENCHMARK CRITICAL EXPERIMENTS OF HIGHLY ENRICHED URANIUM-233 SPHERES REFLECTED BY TUNGSTEN	1995	2
U233-MET-FAST-005	LANL	BENCHMARK CRITICAL EXPERIMENT OF HIGHLY ENRICHED URANIUM-233 SPHERES REFLECTED BY BERYLLIUM	1996	2
U233-MET-FAST-006	LANL	BENCHMARK CRITICAL EXPERIMENT OF A URANIUM-233 SPHERE REFLECTED BY NORMAL URANIUM WITH FLATTOP	1996	1
U233-SOL-INTER-001	LLNL	URANYL-FLUORIDE (233U) SOLUTIONS IN SPHERICAL STAINLESS STEEL VESSELS WITH REFLECTORS OF Be, CH2 AND Be-CH2 COMPOSITES - PART I	2000	33
U233-SOL-THERM-001	ORNL	UNREFLECTED SPHERES OF 233U NITRATE SOLUTIONS	1996	5
U233-SOL-THERM-002	ORNL	PARAFFIN-REFLECTED 8-, 8.5-, 9-, 10-, AND 12-INCH-DIAMETER CYLINDERS OF 233U URANYL NITRATE SOLUTIONS	1999	19
U233-SOL-THERM-003	ORNL	PARAFFIN-REFLECTED 5-, 5.4-, 6-, 6.6-, 7.5-, 8-, 8.5-, 9-, AND 12-INCH-DIAMETER CYLINDERS OF 233U URANYL FLUORIDE SOLUTIONS	2000	18
U233-SOL-THERM-004	ORNL	PARAFFIN-REFLECTED 5-, 6-, AND 7.5-INCH-DIAMETER CYLINDERS OF 233U URANYL NITRATE SOLUTIONS	1998	13
U233-SOL-THERM-005	ORNL	WATER-REFLECTED 233U URANYL NITRATE SOLUTIONS IN SIMPLE GEOMETRY	2001	2
U233-SOL-THERM-006	ORNL	ARRAYS OF 233UO2(NO3)2 AQUEOUS SOLUTIONS CONTAINED WITHIN STAINLESS STEEL CANS	2001	51
U233-SOL-THERM-008	ORNL	A 48-INCH-DIAMETER UNREFLECTED SPHERE OF 233U NITRATE SOLUTION	1997	1
U233-SOL-THERM-009	ORNL	UNREFLECTED LARGE-DIAMETER CYLINDERS OF U233URANYL NITRATE SOLUTIONS	2004	4
U233-SOL-THERM-011	LLNL	URANYL-FLUORIDE (233U) SOLUTIONS IN SPHERICAL STAINLESS STEEL VESSELS WITH REFLECTORS OF Be, CH2 AND Be-CH2 COMPOSITES - PART I	2000	33
U233-SOL-THERM-012	ORNL	WATER-REFLECTED SPHERICAL VESSELS PARTIALLY FILLED OR FILLED WITH 233UO2(NO3)2 SOLUTION	2002	8
U233-SOL-THERM-013	ORNL	UNREFLECTED SPHERICAL VESSELS PARTIALLY FILLED OR FILLED WITH 233UO2(NO3)2 SOLUTION	2003	21
U233-SOL-THERM-014	PNL	LUCITE-MODERATED AND UNMODERATED, REFLECTED AND NON-REFLECTED ARRAYS OF BOTTLES CONTAINING URANYL NITRATE (98.2 WT.% 233U) SOLUTION	2002	18
U233-SOL-THERM-015	LLNL	URANYL-FLUORIDE (233U) SOLUTIONS IN SPHERICAL STAINLESS STEEL VESSELS WITH REFLECTORS OF Be, CH2 AND Be-CH2 COMPOSITES - PART II	2002	31
U233-SOL-THERM-016	ORNL	UNREFLECTED SOLUTIONS OF 233UO2(NO3)2 IN CYLINDERS	2005	33
U233-SOL-THERM-017	ORNL	WATER-REFLECTED SOLUTIONS OF 233UO2(NO3)2 IN CYLINDERS	2005	15
U233-SOL-MIXED-001	LLNL	URANYL-FLUORIDE (233U) SOLUTIONS IN SPHERICAL STAINLESS STEEL VESSELS WITH REFLECTORS OF Be, CH2 AND Be-CH2 COMPOSITES - PART I	2000	33
U233-SOL-MIXED-002	LLNL	URANYL-FLUORIDE (233U) SOLUTIONS IN SPHERICAL STAINLESS STEEL VESSELS WITH REFLECTORS OF Be, CH2 AND Be-CH2 COMPOSITES - PART II	2002	31
U233-COMP-THERM-001	BAPL	LWBR SB CORE EXPERIMENTS	2003	8
U233-COMP-THERM-004	BAPL	D2O MODERATED LATTICE OF 233UO2-232ThO2	2010	1
MIX-MET-FAST-001	LANL	BENCHMARK CRITICAL EXPERIMENT OF A PLUTONIUM SPHERE SURROUNDED BY HIGHLY ENRICHED URANIUM	1995	1
MIX-MET-FAST-002	LANL	SPHERICAL COMPOSITE CORES COMPOSED OF PLUTONIUM AND HIGHLY ENRICHED URANIUM REFLECTED BY NORMAL URANIUM	1997	3
MIX-MET-FAST-007	LLNL	CRITICAL EXPERIMENTS PERFORMED USING SPHERICAL COMPOSITE CORES REFLECTED BY BERYLLIUM	1996	23
MIX-MET-FAST-011	ANL-W	ZPPR-21 PHASES B THROUGH E: CYLINDRICAL ASSEMBLIES OF MIXED FISSILE PU AND U METAL REFLECTED BY GRAPHITE	2001	4
MIX-MET-FAST-013	LANL	PLUTONIUM SPHERE SURROUNDED BY HIGHLY ENRICHED URANIUM	2005	1
MIX-MET-INTER-003	ANL-W	ZPR-3 ASSEMBLY 54: A CYLINDRICAL ASSEMBLY OF PLUTONIUM METAL, DEPLETED URANIUM, AND GRAPHITE WITH A THICK IRON REFLECTOR	2011	1
MIX-MET-INTER-004	ANL-W	ZPR-3 ASSEMBLY 53: A CYLINDRICAL ASSEMBLY OF PLUTONIUM METAL, DEPLETED URANIUM AND GRAPHITE WITH A THICK DEPLETED URANIUM REFLECTOR	2011	1
MIX-SOL-THERM-001	PNL	CRITICALITY EXPERIMENTS WITH MIXED PLUTONIUM AND URANIUM NITRATE SOLUTION AT A PLUTONIUM FRACTION OF 0.2 AND 1.0 IN ANNULAR CYLINDRICAL GEOMETRY	1995	13
MIX-SOL-THERM-002	PNL	CRITICALITY EXPERIMENTS WITH MIXED PLUTONIUM AND URANIUM NITRATE SOLUTION AT A PLUTONIUM FRACTION OF 0.2 AND 0.5 IN LARGE CYLINDRICAL GEOMETRY	1995	3
MIX-SOL-THERM-004	PNL	CRITICALITY EXPERIMENTS WITH MIXED PLUTONIUM AND URANIUM NITRATE SOLUTION AT A PLUTONIUM FRACTION OF 0.4 IN SMALL CYLINDRICAL GEOMETRY	1996	9
MIX-SOL-THERM-005	PNL	CRITICALITY EXPERIMENTS WITH MIXED PLUTONIUM AND URANIUM NITRATE SOLUTION AT A PLUTONIUM FRACTION OF 0.4 IN SLAB GEOMETRY	1997	8
MIX-SOL-THERM-007	PNL	WATER-REFLECTED PLUTONIUM-URANYL NITRATE SOLUTION CONTAINING GADOLINIUM	2004	10
MIX-SOL-THERM-008	PNL	PLUTONIUM (5.7% 240PU), DEPLETED-URANIUM NITRATE SOLUTIONS (240-270 G/LITER OF PU+U AND PU:U ≅ 1:2) IN A WATER-REFLECTED CYLINDRICAL TANK FILLED WITH BORATED-GLASS RASCHIG RINGS	2005	8
MIX-SOL-THERM-010	PNL	WATER-REFLECTED PLUTONIUM-URANYL NITRATE SOLUTION CONTAINING BORON AND GADOLINIUM	2006	9
MIX-COMP-FAST-001	ANL	ZPR-6 ASSEMBLY 7: A CYLINDRICAL ASSEMBLY WITH MIXED (PU,U)-OXIDE FUEL AND SODIUM WITH A THICK DEPLETED-URANIUM REFLECTOR	2003	1
MIX-COMP-FAST-002	ANL	ZPR-6 ASSEMBLY 7 HIGH 240PU CORE: A CYLINDRICAL ASSEMBLY WITH MIXED (PU,U)-OXIDE FUEL AND A CENTRAL HIGH 240PU ZONE	2007	1
MIX-COMP-FAST-003	ANL-W	ZPR-3 ASSEMBLIES 48 AND 48B: CYLINDRICAL ASSEMBLIES OF MIXED (PU,U), GRAPHITE AND SODIUM WITH A DEPLETED URANIUM BLANKET	2009	2
MIX-COMP-FAST-004	ANL-W	ZPR-3 ASSEMBLY 56B: A CYLINDRICAL ASSEMBLY OF MIXED (PU,U), OXIDE AND SODIUM WITH A NICKEL-SODIUM REFLECTOR	2009	1
MIX-COMP-FAST-005	ANL	ZPR-9 ASSEMBLY 31: A CYLINDRICAL ASSEMBLY WITH MIXED (PU,U)-CARBIDE FUEL AND DEPLETED URANIUM CARBIDE BLANKET	2012	1
MIX-COMP-FAST-006	ANL-W	ZPPR-2: A CYLINDRICAL ASSEMBLY WITH MIXED (PU,U)-OXIDE FUEL AND SODIUM REFLECTED BY DU, SODIUM AND STEEL	2012	1
MIX-COMP-INTER-006	PNL	2.8 & 2.86 H:[Pu+U] REFLECTED AND UN-REFLECTED, POLYSTYRENE-MODERATED, MIXED OXIDE BLOCKS WITH AND WITHOUT FIXED ABSORBER PLATES (Copper, Copper containing 1 wt.% Cadmium, and Aluminum)	2005	21
MIX-COMP-THERM-001	PNL	WATER-REFLECTED MIXED PLUTONIUM-URANIUM OXIDE (20 WT.% PU) PINS	1996	4
MIX-COMP-THERM-002	PNL	RECTANGULAR ARRAYS OF WATER-MODERATED UO2-2 Wt.% PUO2 (8% 240Pu) FUEL RODS	1997	6
MIX-COMP-THERM-003	Westinghouse	RECTANGULAR ARRAYS OF WATER-MODERATED UO2-6.6 WT.% PUO2 FUEL RODS	1997	6
MIX-COMP-THERM-005	PNL	WATER-MODERATED MIXED PLUTONIUM-URANIUM OXIDE PINS, 4.0 WT.% PUO2, 18% 240Pu, NATURAL URANIUM	1999	7
MIX-COMP-THERM-006	PNL	WATER-MODERATED MIXED OXIDE HEXAGONAL LATTICES - 2.0 WT.% PUO2, 8% 240PU, NATURAL URANIUM	2000	50
MIX-COMP-THERM-007	PNL	HEXAGONAL LATTICES OF MIXED OXIDE FUEL PINS UO2 - 2 Wt.% PUO2 (16% 240Pu), NATURAL URANIUM	1999	27
MIX-COMP-THERM-008	PNL	HEXAGONAL LATTICES OF MIXED OXIDE FUEL PINS UO2 – 2.0 WT.% PUO2, 24% 240Pu, NATURAL URANIUM	1999	28
MIX-COMP-THERM-009	PNL	MIXED-OXIDE FUEL-PIN LATTICE – 1.5 WT.% PUO2, 8% 240 Pu, DEPLETED URANIUM	1999	6
MIX-COMP-THERM-012	PNL	REFLECTED AND UNREFLECTED POLYSTYRENE-MODERATED, MIXED OXIDE CUBES AND SLABS	2001	33
MIX-COMP-THERM-013	PNL	REFLECTED, POLYSTYRENE-MODERATED, MIXED OXIDE BLOCKS WITH FIXED ABSORBER PLATES	2004	31
MIX-COMP-THERM-014	PNL	REFLECTED, POLYSTYRENE-MODERATED, MIXED OXIDE BLOCKS WITH FIXED ABSORBER PLATES OF CU, CU-CD AND AL	2004	22
MIX-COMP-THERM-016	PNL	2.8 H:[Pu+U] (with a 30.6 H:[Pu+U] driver region) REFLECTED, POLYSTYRENE-MODERATED, MIXED OXIDE BLOCKS WITH FIXED ABSORBER PLATES (Stainless Steel, Borated Stainless Steel, Depleted Uranium, Boral, Cadmium, Lead, Aluminum)	2005	19
MIX-COMP-MIXED-001	PNL	2.8 & 2.86 H:[Pu+U] REFLECTED AND UN-REFLECTED, POLYSTYRENE-MODERATED, MIXED OXIDE BLOCKS WITH AND WITHOUT FIXED ABSORBER PLATES (Copper, Copper containing 1 wt.% Cadmium, and Aluminum)	2005	21
MIX-MISC-THERM-001	PNL	MIXED OXIDE FUEL-PIN LATTICE IN PLUTONIUM-URANIUM NITRATE SOLUTION	1999	11
MIX-MISC-THERM-004	PNL	WATER-REFLECTED TRIANGULAR-PITCHED LATTICE OF MIXED OXIDE FUEL RODS IMMERSED IN PLUTONIUM / URANYL NITRATE SOLUTION CONTAINING GADOLINIUM	2003	6
MIX-MISC-THERM-005	PNL	WATER-REFLECTED TRIANGULAR-PITCHED LATTICE OF MIXED OXIDE FUEL RODS IMMERSED IN PLUTONIUM-URANYL NITRATE SOLUTION CONTAINING BORON AND GADOLINIUM	2005	7
SPEC-MET-FAST-001	LANL	REPLACEMENT MEASUREMENTS PERFORMED WITH CURIUM-244, PLUTONIUM-239, AND HEU USING JEZEBEL	1996	3
SPEC-MET-FAST-002	LANL	PLUTONIUM-238 AND PLUTONIUM-239 REPLACEMENT MEASUREMENTS PERFORMED USING JEZEBEL	1997	3
SPEC-MET-FAST-003	LANL	NEPTUNIUM-237 AND HIGHLY ENRICHED URANIUM REPLACEMENT MEASUREMENTS PERFORMED USING FLATTOP	1997	5
SPEC-MET-FAST-004	LANL	CRITICAL EXPERIMENTS PERFORMED USING PLATES OF PLUTONIUM-242, HEU, AND PLUTONIUM-239	1998	7
SPEC-MET-FAST-008	LANL	NEPTUNIUM-237 SPHERE SURROUNDED BY HEMISPHERICAL SHELLS OF HIGHLY ENRICHED URANIUM	2003	1
SPEC-MET-FAST-011	LANL	NEPTUNIUM-237 SPHERE SURROUNDED BY HIGHLY ENRICHED URANIUM AND REFLECTED BY POLYETHYLENE	2005	1
SPEC-MET-FAST-014	LANL	NEPTUNIUM-237 SPHERE SURROUNDED BY HIGHLY ENRICHED URANIUM AND REFLECTED BY LOW-CARBON STEEL	2004	1
SUB-PU-MET-FAST-001	LANL	POLYETHYLENE-REFLECTED PLUTONIUM METAL SPHERE SUBCRITICAL NOISE MEASUREMENTS	2003	5
SUB-HEU-MET-FAST-001	ANL-W	ZPPR-20 PHASE E: A CYLINDRICAL ASSEMBLY OF U METAL REFLECTED BY BERYLLIUM OXIDE AND SAND	2005	1
SUB-HEU-MET-THERM-001	MURR	WATER MODERATED U(93.15 wt.%) ALUMINUM RESEARCH REACTOR FUEL ELEMENT SUBCRITICAL NOISE MEASUREMENTS	2006	2
SUB-HEU-MET-THERM-002	MURR	WATER MODERATED U (93.15 wt.%) ALUMINUM RESEARCH REACTOR FUEL ELEMENT SUBCRITICAL NOISE MEASUREMENTS WITH STRONG NEUTRON ABSORBING MATERIALS	2007	7
SUB-HEU-MET-MIXED-001	ANL-W	ZPPR-20 PHASE D: A CYLINDRICAL ASSEMBLY OF POLYETHYLENE-MODERATED U METAL REFLECTED BY BERYLLIUM OXIDE AND POLYETHYLENE	2005	1
SUB-HEU-SOL-THERM-001	ORNL	UNREFLECTED HIGH-ENRICHED URANYL NITRATE SUBCRITICAL NOISE MEASUREMENTS	2000	6
SUB-HEU-SOL-THERM-002	LANL	SUBCRITICAL NOISE MEASUREMENTS FOR TWO COAXIAL CYLINDRICAL TANKS CONTAINING 93.1% URANYL NITRATE SOLUTION	2008	3

Contact

cps-icsbep@oecd-nea.org

Activities

results

Database for ICSBEP (DICE)

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments (DICE) in 2001.

See

International Criticality Safety Benchmark Evaluation Project (ICSBEP)

The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allows criticality safety analysts to easily use the data to validate calculation tools and cross-section libraries.

See

International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various critical facilities around the world.

See

Nuclear Science Committee (NSC)

The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.

Working Party on Nuclear Criticality Safety (WPNCS)

The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investigations of static and transient configurations encountered in the nuclear fuel cycle. These include fuel fabrication, transport and storage.

See