Intracell Flux Traverses and Thermal Utilizations for 1.15% Enriched Uranium Rods in Ordinary Water
- Brookhaven National Laboratory (BNL), Upton, NY (United States)
The measurements reported are those of the special distribution of thermal neutrons in typical lattice cells of slightly enriched uranium rod-ordinary water assemblies. Flux traverses were made both with pure water and boron poisoned water for the moderator. The detectors used were small foils of dysprosium oxide dispersed in lucite or polyethelene.
- Research Organization:
- Brookhaven National Laboratory (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(30-2)-GEN-16
- NSA Number:
- NSA-10-003946
- OSTI ID:
- 4377606
- Report Number(s):
- BNL-1987
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Analysis
BORON
CRITICAL ASSEMBLIES
Critical Assemblies
Criticality
DISTRIBUTION
DYSPROSIUM OXIDES
Dysprosium Oxides
ENRICHMENT
Enriched Uranium
FOILS
FUEL ELEMENTS
Lucite
MEASURED VALUES
NEUTRON DETECTION
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
POISONING
POLYETHYLENES
POLYMERS
REACTOR CORE
RODS
Safety
THERMAL NEUTRONS
THERMAL UTILIZATION
URANIUM
WATER MODERATOR
ZONES
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Analysis
BORON
CRITICAL ASSEMBLIES
Critical Assemblies
Criticality
DISTRIBUTION
DYSPROSIUM OXIDES
Dysprosium Oxides
ENRICHMENT
Enriched Uranium
FOILS
FUEL ELEMENTS
Lucite
MEASURED VALUES
NEUTRON DETECTION
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
POISONING
POLYETHYLENES
POLYMERS
REACTOR CORE
RODS
Safety
THERMAL NEUTRONS
THERMAL UTILIZATION
URANIUM
WATER MODERATOR
ZONES