International Reactor Physics Benchmark Experiments (IRPhE) Project

Handbook contents 2017 edition

Denotes new items in the 2017 edition

Evaluations Title
FUND
ATR-FUND-RESR-001 Advanced Test Reactor: Serpentine Arrangement of Highly Enriched Water-Moderated Uranium-Aluminide Fuel Plates Reflected by Beryllium
BFS1-FUND-EXP-001 Experimental Program Performed at the BFS-97, -99, -101 Assemblies - Critical Experiments with Heterogeneous Compositions of Plutonium, Depleted Uranium Dioxide and Polyethylene
BFS1-FUND-EXP-002 Experimental Program Performed at the BFS-42 Assembly - k-infinity Experiments for 238U in Fast Neutron Spectra: Measurements with Plutonium Mixed with Depleted Uranium Dioxide and Polyethylene
BFS1-FUND-EXP-003 Experimental Program Performed at the BFS-57and -59 Assemblies - Critical Experiments with Heterogeneous Compositions of Enriched Uranium or Plutonium, Depleted Uranium Dioxide and Polyethylene
BFS1-FUND-EXP-004 BFS-49 Assemblies: Critical Experiments with Heterogeneous Compositions of Plutonium, Depleted-Uranium Dioxide, and Polyethylene
BFS2-FUND-EXP-001 Experimental Program Performed at the BFS-31 Assemblies - k-infinity Experiments for 238U in Fast Neutron Spectra: Measurements with Plutonium Mixed with Depleted Uranium Dioxide
CORAL(I)-FUND-RESR-001 CIEMAT First Criticality of CORAL-I Reactor, a 90%-Enriched Uranium Cylinder Reflected by Natural Uranium, both Metal
FR0-FUND-RESR-001 The Fr0 Series 1: Copper-Reflected "Cylindrical" Uranium (20 % 235U) Metal
FR0-FUND-RESR-002 The Fr0 Series 4: 20%-Enriched "Cylindrical" Uranium Metal Reflected by Natural Uranium
FR0-FUND-RESR-003 The Fr0 Experiments with Diluted 20%-enriched "Cylindrical" Uranium Metal Reflected by Copper
HECTOR-FUND-EXP-001 K-Infinity Experiments in Intermediate Neutron Spectra for 239Pu
HECTOR-FUND-EXP-002 K-Infinity Experiments in Intermediate Neutron Spectra for 235U
IGR-FUND-RESR-001 IGR Reactor – Uranium-Graphite Blocks Reflected by Graphite
KUCA-FUND-RESR-001 Evaluation of the Kyoto University Critical Assembly Erbium Oxide Experiments
LAMPRE-FUND-RESR-001 Critical Experiments Performed for LAMPRE, the Los Alamos Molten Plutonium Reactor
MINERVE-FUND-RESR-001 Reactivity Worth Measurement of Major Fission Products in Minerve LWR-Lattice Experiment
NRAD-FUND-RESR-001 Fresh-Core Reload of the Neutron Radiography (NRAD) Reactor with uranium(20)-Erbium-Zirconium-Hydride Fuel
NRAD-FUND-RESR-002 Neutron Radiography (NRAD) Reactor 64-element Core Upgrade
ORSPHERE-FUND-EXP-001 Orsphere: Physics Measurements for Bare, HEU(93.2)-metal Sphere
PBF-FUND-RESR-001 Power Burst Facility: U(18)O2-CaO-ZrO2 Fuel Rods in Water
RA6-FUND-RESR-001 RA-6 Reactor: Water Reflected, Water Moderated U(19.77)3Si2-Al Fuel Plates
RB-FUND-EXP-001 RB Reactor: Natural Uranium Metal Rods and 2% Enriched Uranium Metal Fuel Elements in Lattice of Heavy Water - Core Rb5/1973
RB-FUND-EXP-002 RB Reactor, Core RB39/1978:Natural Uranium Metal Rods and 2 % Enriched Uranium Metal Fuel Elements in Heavy Water, Including Experiments to Characterise the Coupled External Neutron Converter
RB-FUND-EXP-003 RB Reactor: Natural-Uranium Rods in Heavy Water
RB-FUND-EXP-004 RB Reactor: Lattices of 2%-Enriched Uranium Elements in Heavy Water
RB-FUND-EXP-005 RB Reactor: Fuel Assemblies Substitution Criticality Experiments in Lattices of 2%-Enriched Uranium in Heavy Water
RB-FUND-EXP-006 RB Reactor: Lattices of 80%-Enriched Uranium Elements in Heavy Water
RB-FUND-EXP-007 RB Reactor: VINET – Experimental Fuel Channel (EFC), Core RB58/1982
RB-FUND-EXP-008 RB Reactor: Internal Neutron Converters (Inc), Cores RB59/1983, RB60/1984 and RB61/1984
RHF-FUND-RESR-001 Evaluation of Measurements Performed on the French High Flux Reactor (RHF)
TRIGA-FUND-RESR-001 Triga Mark II Reactor: U(20) – Zirconium Hydride Fuel Rods in Water with Graphite Reflector
TRIGA-FUND-RESR-002 Reaction Rate Distribution Experiments at the Slovenian JSI TRIGA MARK II Research Reactor
ZEBRA-FUND-RESR-001 K-Infinity Measurements in Zebra Core 8
ZPR-FUND-EXP-001 ZPR-3 Assembly 6f: A Spherical Assembly of Highly Enriched Uranium, Depleted Uranium, Aluminum and Steel with an Average 235U Enrichment of 47 atom %
ZPR-FUND-EXP-002 ZPR-3 Assembly 6f: A Spherical Assembly of Highly Enriched Uranium, Depleted Uranium, Aluminum and Steel with an Average 235U Enrichment of 47 atom %
ZPR-FUND-EXP-003 ZPR-3 Assembly 12: A Cylindrical Assembly of Highly Enriched Uranium, Depleted Uranium and Graphite with an Average 235U Enrichment of 21 atom %
ZPR-FUND-EXP-004 ZPR-3 Assembly 23: A Cylindrical Assembly of U Metal (93% 235U) and Aluminum Reflected by Depleted-Uranium
ZPR-FUND-EXP-005 ZPR-3 Assembly 41: A Cylindrical Assembly of U metal (16% 235U), Aluminum, and Steel, Reflected by Depleted-Uranium
ZPR-FUND-EXP-006 ZPR-3 Assembly 53: A Cylindrical Assembly of Plutonium Metal, Depleted Uranium and Graphite with a Thick Depleted Uranium Reflector
ZPR-FUND-EXP-007 ZPR-3 Assembly 54: A Cylindrical Assembly of Plutonium Metal, Depleted Uranium, and Graphite with a Thick Iron Reflector
ZPR-FUND-EXP-008 ZPR-6 Assembly 6a: A Cylindrical Assembly with Uranium Oxide Fuel and Dodium with a Thick Depleted-Uranium Blanket
ZPR-FUND-EXP-009 ZPR-6 Assembly 10: A Cylindrical Plutonium/Carbon/Stainless Steel Assembly with Stainless Steel and Iron Reflectors
ZPR-FUND-EXP-010 ZPR-9 Assembly 1: A Cylindrical Assembly of U Metal (93% 235U) and Depleted Uranium with Aluminum Reflectors
ZPR-FUND-EXP-011 ZPR-9 Assemblies 2 and 3: Cylindrical Assemblies of U Metal and Tungsten with Aluminum Reflectors
ZPR-FUND-EXP-012 ZPR-9 Assembly 4: A Cylindrical Assembly of U Metal (93% 235U) and Tungsten with Aluminum Reflectors
ZPR-FUND-EXP-013 ZPR-9 Assemblies 5 and 6: HEU (93% 235U) Cylindrical Cores with Tungsten, Graphite, and Aluminum Diluents with a Dense Aluminum Reflector
ZPR-FUND-EXP-014 ZPR-9 Assembly 31: A Cylindrical Assembly with Mixed (Pu,U)-Carbide Fuel and Depleted Uranium Carbide Blanket
ZPR-FUND-EXP-015 The Uranium/Iron Cenchmark Assembly: A 235U(93%)/Iron Cylinder Reflected by Stainless Steel
ZPR-FUND-EXP-016 The U9 Benchmark Assembly: A Cylindrical Assembly of U metal (9% 235U) with a Thick Depleted-Uranium Reflector
ZPR-FUND-EXP-017 ZPR-3 Assembly 58: A Cylindrical Assembly of Plutonium Metal and Graphite with a Thick Depleted Uranium Reflector
ZPR-FUND-EXP-018 ZPR-3 Assembly 59: A Cylindrical Assembly of Plutonium Metal and Graphite with a Thick Lead Reflector
GCFR
PROTEUS-GCFR-RESR-001 GCFR-PROTEUS Experimental Program Core 11: Homogeneous MOX Fuel Test Region
GCR
ASTRA-GCR-EXP-001 Graphite Annular Core Assemblies with Fuel Elements Containing UO2 Coated Fuel Particles
HTR10-GCR-RESR-001 Evaluation of the Initial Critical Configuration of the HTR-10 Pebble-Bed Reactor
HTTR-GCR-RESR-001 Evaluation of the Start-Up Core Physics Tests at Japan’s High Temperature Engineering Test Reactor (Fully-Loaded Core)
HTTR-GCR-RESR-002 Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Annular Core Loadings)
HTTR-GCR-RESR-003 Evaluation of Zero-Power, Elevated-Temperature Measurements at Japan's High Temperature Engineering Test Reactor
PROTEUS-GCR-EXP-001 HTR-Proteus Pebble Bed Experimental Program Cores 1, 1A, 2, and 3: Hexagonal Close Packing with a 1:2 Moderator-to-Fuel Pebble Ratio
PROTEUS-GCR-EXP-002 HTR-proteus Pebble Bed Experimental Program Core 4 Random Packing with a 1:1 Moderator-to-fuel Pebble Ratio
PROTEUS-GCR-EXP-003 HTR-proteus Pebble Bed Experimental Program Cores 5, 6, 7, & 8: Columnar Hexagonal Point-on-point Packing with a 1:2 Moderator-to-fuel Pebble
PROTEUS-GCR-EXP-004 HTR-proteus Pebble Bed Experimental Program Cores 9 & 10: Columnar Hexagonal Point-on-point Packing with a 1:1 Moderator-to-fuel Pebble Ratio
VHTRC-GCR-EXP-001 Temperature Effect on Reactivity in VHTRC-1 Core
HWR
DCA-HWR-RESR-001 Deuterium Critical Assembly with 1.2% Enriched Uranium Varying Coolant Void Fraction and Lattice Pitch
ETA-HWR-EXP-001 ETA-I: D2O Moderated Lattice of UO2-Th2
ETA-HWR-EXP-002 D2O Moderated Lattice of 233UO2-232Th2
ZED2-HWR-EXP-001 28-Element Natural UO2 Fuel Assemblies in ZED-2
ZED2-HWR-EXP-002 ZED-2 reactor: Natural-Uranium Metal Fuel Assemblies in Heavy-water
LMFR
BFS1-LMFR-EXP-001 BFS-73-1 Assembly: Experimental Model of Sodium-Cooled Fast Reactor with Core of Metal Uranium Fuel of 18.5% Enrichment and Depleted Uranium Dioxide Blanket
BFS1-LMFR-EXP-002 BFS-61 Assemblies: Experimental Model of Lead-Cooled Fast Reactor with Core of Metal Plutonium-Depleted Uranium Fuel and Different Reflectors
BFS2-LMFR-EXP-001 BFS-62-3A Experiment: Fast Reactor Core with U and U-Pu fuel of 17% Enrichment and Partial Stainless Steel Reflector
BR2-LMFR-RESR Fast Reactor with Plutonium Metal Fuel and Mercury Coolant
FFTF-LMFR-RESR-001 Evaluation of the Initial Isothermal Physics Measurements at the Fast Flux Test Facility, a Prototypic Liquid Metal Fast Breeder Reactor
JOYO-LMFR-RESR-001 Japan's Experimental Fast Reactor JOYO MK-Icore: Sodium-Cooled Uranium=Plutonium Mixed Oxide Fueled Fast Core Surrounded by UO2 Blanket
SNEAK-LFMR-EXP-001 SNEAK 7A and 7B PU-Fueled Fast Critical Assemblies in the Karlsruhe Fast Critical Facility
ZEBRA-LMFR-EXP-001 Fast Critical Experiments in Plate and Pin Geometry Form. The ZEBRA CADENZA Cores, Assemblies 22, 23, 24 and 25
ZEBRA-LMFR-EXP-002 The ZEBRA MOZART Programme Part 1. MZA and MZB, ZEBRA Assemblies 11 and 12
ZEBRA-LMFR-EXP-003 The ZEBRA MOZART Programme Part 2. MZC and the Control Rod Studies - ZEBRA Assembly 12/4 and 12/5
ZPPR-LMFR-EXP-001 ZPPR-10A Experiment: A 650 MWe-Class Sodium-Cooled MOX-Fueled FBR Homogeneous Core Mock-Up Critical Experiment with Two Enrichment Zones and Nineteen Control Rod Positions
ZPPR-LMFR-EXP-002 ZPPR-9 Experiment: A 650 MWe-Class Sodium-Cooled Mox-Fueled FBR Core Mock-Up Critical Experiment with Clean Core of Two Homogeneous Zones
ZPPR-LMFR-EXP-003 ZPPR-18A Experiment: A 1,000 MWe-Class Sodium-Cooled MOX-Fueled FBR Core Mock-Up Critical Experiment with Two-Homogeneous Zones and Control-Rod Withdrawal, where Enriched Uranium is used with the Shape of a Sector in the Outer Core
ZPPR-LMFR-EXP-004 ZPPR-19B Experiment: A 1,000 MWe-Class Sodium-Cooled MOX-Fueled FBR Core Mock-Up Critical Experiment with Two-Homogeneous Zones and Control-Rod Withdrawal, where Plutonium and Enriched Uranium are used Mixing in the Outer Core
ZPPR-LMFR-EXP-005 ZPPR-10B Experiment: A 650 MWe-Class Sodium-Cooled MOX-Fueled FBR Homogeneous Core Mock-Up Critical Experiment with Two Enrichment Zones, Seven Control Rods and Twelve Control Rod Positions
ZPPR-LMFR-EXP-006 ZPPR-10C Experiment: A 800 MWe-Class Sodium-Cooled MOX-Fueled FBR Homogeneous Core Mock-Up Critical Experiment with Two Enrichment Zones and Nineteen Control Rod Positions
ZPPR-LMFR-EXP-007 ZPPR-13A Experiment: A 650 MWe-Class Sodium-Cooled MOX-Fueled FBR Radial Heterogeneous Core Mock-Up Critical Experiment with Central Blanket Zone and Two Internal Blanket Rings
ZPPR-LMFR-EXP-008 ZPPR-18C Experiment: A 1,000 MWe-Class Sodium-Cooled MOX-Fueled FBR Homogeneous Core Mock-Up Critical Experiment in the State of Removal of One of Eighteen Half-Inserted Control Rods, where Enriched Uranium is used with the Shape of a Sector in the Outer Core
ZPPR-LMFR-EXP-009 ZPPR-17A Experiment: A 650 MWe-Class Sodium-Cooled Mox-Fueled FBR Axial Heterogeneous Core Mock-Up Critical Experiment with Central Internal Blanket Zone
ZPPR-LMFR-EXP-010 ZPPR-12: Mockup of the 400 MWe Sodium-cooled Clinch River Breeder Reactor
ZPPR-LMFR-EXP-011 ZPPR-2: A Cylindrical Assembly with Mixed (Pu,U)-Oxide Fuel and Sodium Reflected by Du, Sodium and Steel
ZPR-LMFR-EXP-001 ZPR-6 Assembly 7: A Cylindrical Assembly with Mixed (Pu,U)-Oxide Fuel and Sodium with a Thick Depleted-Uranium Reflector
ZPR-LMFR-EXP-002 ZPR-6 Assembly 7 with High Pu-240: A Fast Reactor Core With Mixed (Pu,U)-Oxide Fuel and Sodium and High Pu-240 Zone
ZPR-LMFR-EXP-003 ZPR-3 Assemblies 48 and 48b: Cylindrical Assemblies of Mixed (Pu,U), Graphite and Sodium with a Depleted Uranium Blanket
ZPR-LMFR-EXP-004 ZPR-3 Assembly 56b: A Cylindrical Assembly of Mixed (Pu,U), Oxide and Dodium with a Nickel-Sodium Reflector
LWR
CROCUS-LWR-RESR-001 Kinetic Parameters and Reactivity Effect Experiments in CROCUS
DIMPLE-LWR-RESR-001 Light Water Moderated and Reflected Low Enriched Uranium (3 wt.% 235U) Dioxide Rod Lattices DIMPLE S01
DIMPLE-LWR-RESR-002 Light Water Moderated and Reflected Low Enriched Uranium (3 wt.% 235U) Dioxide Rod Lattices DIMPLE S06
IPEN(MB01)-LWR-RESR-001 Isothermal Experiment of the IPEN/MB-01 Reactor
IPEN(MB01)-LWR-RESR-002 Critical Loading Configurations of the IPEN/Mb-01 Reactor with a Heavy SS-304 Reflector
IPEN(MB01)-LWR-RESR-003 Critical Loading Configurations of the IPEN/Mb-01 Reactor with UO2, Stainless Steel and Copper Rods
IPEN(MB01)-LWR-RESR-004 Critical Loading Configurations of the IPEN/Mb-01 Reactor Considering Temperature Variation from 14°C to 85°C
IPEN(MB01)-LWR-RESR-005 Critical Loading Configurations of the IPEN/Mb-01 Reactor with UO2, and UO2-Gd2O3 Rods
IPEN(MB01)-LWR-RESR-006 Critical Loading Configurations of the IPEN/Mb-01 Reactor with Large Void in the Reflector
IPEN(MB01)-LWR-RESR-007 Critical Loading Configurations of the IPEN/Mb-01 Reactor with Low Enriched Fuel and Burnable Poison Rods
IPEN(MB01)-LWR-RESR-008 Critical Loading Configurations of the IPEN/Mb-01 Reactor with a Big Central Void
IPEN(MB01)-LWR-RESR-009 Critical Loading Configurations of the IPEN/Mb-01 Reactor with a Central Cruciform Rod
IPEN(MB01)-LWR-RESR-010 Critical Loading Configurations of the IPEN/Mb-01 Reactor with UO2 and Borated Stainless Steel Plates
IPEN(MB01)-LWR-RESR-011 Critical Loading Configurations of the IPEN/Mb-01 Reactor with UO2 and Stainless Steel Rods
IPEN(MB01)-LWR-RESR-012 Critical Loading Configurations of the IPEN/Mb-01 Reactor with UO2, Stainless Steel and Gd2O3 Rods
IPEN(MB01)-LWR-RESR-013 Critical Loading Configurations of the Ipen/Mb-01 Reactor with Soluble Boron
IPEN(MB01)-LWR-RESR-014 Subcritical Experiments in the IPEN/Mb-01 Research Reactor Facility
IPEN(MB01)-LWR-RESR-015 Critical Loading Configurations of the IPEN/Mb-01 Reactor with Heavy Reflectors Composed of Carbon Steel and Nickel
IPEN(MB01)-LWR-RESR-016 Subcritical Loading Configurations of the IPEN/MB-01 Reactor
IPEN(MB01)-LWR-RESR-017 The Inversion Point of the Isothermal Reactivity Coefficient of the IPEN/MB-01 Reactor
IPEN(MB01)-LWR-RESR-018 Critical Loading Configurations of the IPEN/MB-01 Reactor Composed of Fuel and Molybdenum Rods
KRITZ-LWR-RESR-001 KRITZ-2:19 Experiment on Regular H2O/Fuel Pin Lattices with Mixed Oxide Fuel at Temperatures 21.1 and 235.9 °C
KRITZ-LWR-RESR-002 KRITZ-2:1 Experiment on Regular H2O/Fuel Pin Lattices with Low Enriched Uranium Fuel at Temperatures 19.7 °C and 248.5 °C
KRITZ-LWR-RESR-003 KRITZ-2:13 Experiment on Regular H2O/Fuel Pin Lattices with Low Enriched Uranium Fuel at Temperatures 22.1 °C and 243 °C
TCA-LWR-EXP-001 Temperature Effects on Reactivity in Light Water Moderated UO2 Core with Soluble Poisons at TCA
TCA-LWR-EXP-002 2.6%-Enriched UO2 Rods in Light-Water Moderator with Borated Stainless Steel Plate: Single Arrays
TCA-LWR-EXP-003 Critical Configurations of 2.6%-Enriched UO2 Rod Arrays in light-Water Moderator with Borated Stainless Steel Plate: Coupled Arrays
PWR
CREOLE-PWR-EXP-001 CREOLE PWR Reactivity Temperature Coefficient Experiment - UOX and MOX up to 300 °C in EOLE
DIMPLE-PWR-EXP-001 Light-Water Moderated and Reflected Low-Enriched Uranium (3 wt.% 235U) Dioxide Rod Lattices with Discrete Poison-Rod Arrays
DIMPLE-PWR-EXP-002 Light-Water Moderated and Reflected Low-Enriched Uranium (3 wt.% 235U) Dioxide Rod Lattices with Ex-Core Detector Feature
DUKE-PWR-POWER-001 DRAFT - PWR Fuel Assembly Depletion Reactivity Determination using PWR Fission Rate Measurements
EOLE-PWR-EXP-001 Undermoderated Mox (11 wt.% PuO2) Lattice in the EOLE Reactor
OTTOHAHN-PWR-RESR-001 PWR Type UO2 Fuel Rods with Enrichments of 3.5 and 6.6 wt.% with Burnable Absorber ("Otto Hahn" Nuclear Ship Program, Second Core)
SSCR-PWR-EXP-001 B&W Spectral Shift Reactor Lattice Experiment: A 484 Uranium Rods Critical Experiment with Infinite Radial Reflector
SSCR-PWR-EXP-002 B&W Spectral Shift Reactor Lattice Experiment: A 2188 Uranium-Thorium Rods Critical Experiment Moderated by Heavy-light Water Mixture
VENUS-PWR-EXP-001 Draft - VENUS-1 PWR UO2 Core 2-Dimensional Benchmark Experiment
VENUS-PWR-EXP-003 Draft - VENUS-3 PWR UO2 Core 3-Dimensional Benchmark Experiment
VENUS-PWR-EXP-004 Experimental Study of the VENUS Configuration No.7
VENUS-PWR-EXP-005 Experimental Study of the VENUS-PRP Configuration No. 9
RBMK(CF)
RBMKCF-RBMK-EXP-001 RBMK Graphite Reactor: Uniform Configurations of U(1.8, 2.0, or 2.4% 235U)m 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
VVER
LR(0)-VVER-EXP-003 VVER-1000 Physics Experiments Hexagonal Lattices (1.275 Cm Pitch) of Low Enriched U(3.3 Wt.% U235)O2 Fuel Assemblies in Light Water with Graphite and Fluoride Salt Insertions in Central Assembly
LR(0)-VVER-RESR-001 VVER Physics Experiments: Hexagonal Lattices of Low-Enriched U(2.0 – 3.3 wt.% U235)O2 Fuel Assemblies in Light Water with Central Control-Assembly Mockup
LR(0)-VVER-RESR-002 VVER-1000 Mock-up Physics Experiments Hexagonal Lattices
(1.275 cm Pitch) of Low Enriched U(2.0, 3.0, 3.3 wt.% 235U)O2 Fuel
PFACILITY-VVER-EXP-001 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 Aluminium Tubes
ZR6-VVER-EXP-001 The VVER Experiments: Regular and Perturbed Hexagonal Lattices of Low-Enriched UO2 Fuel Rods in Light Water
SPACE
ORCEF-SPACE-EXP-001 Fast Neutron Spectrum Potassium worth for Space Power Reactor Design Validation
SCCA-SPACE-EXP-001 (previously named SCCA-FUND-EXP-001) Critical Configuration and Physics Measurements for Graphite Reflected Assemblies of U(93.15)O2 Fuel Rods (1.27-cm Pitch)
SCCA-SPACE-EXP-002 Critical Configuration and Physics Measurements for Assemblies of U(93.15)O2 Fuel Rods (1.506-cm pitch)
SCCA-SPACE-EXP-003 Critical Configuration and Physics Measurements for Beryllium Reflected Assemblies of U(93.15)O2 Fuel Rods (1.506-cm pitch)
TOPAZ-SPACE-RESR-001 Intermediate Heterogeneous Assembly with Highly Enriched Uranium Dioxide (96% 235u) and Zirconium Hydride Moderator
TOPAZ-SPACE-RESR-002 ) Intermediate Heterogeneous Assembly with Highly Enriched Uranium Dioxide and Sand/Water Radial Reflector
UKS1M-SPACE-EXP-001 Beryllium- and Molybdenum-Reflected Cylinders of Highly Enriched Uranium
ZPPR-SPACE-EXP-001 ZPPR-20 Phase c: A cylindrical Assembly of U Metal Reflected by Beryllium Oxide
ZPPR-SPACE-EXP-002 ZPPR-20 Phase d: A Cylindrical Assembly of Polyethylene-Moderated U Metal Reflected by Beryllium Oxide and Polyethylene
ZPPR-SPACE-EXP-003 ZPPR-20 Phase e: A Cylindrical Assembly of U Metal Reflected by Beryllium Oxide and Sand
ZPPR-SPACE-EXP-004 ZPPR-20 Phase d: A Cylindrical Assembly of Polyethylene-Moderated U Metal Reflected by Beryllium Oxide and Polyethylene
ZPR-SPACE-EXP-001 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

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Last reviewed: 14 April 2017

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