skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Survey of the Static Nuclear Characteristics of Small, One-Region Slurry Reactors

Technical Report ·
DOI:https://doi.org/10.2172/4286111· OSTI ID:4286111
 [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
+ Show Author Affiliations

Survey calculations were made of the criticality characteristics of some small one-region thorium-oxide slurry reactors. Fuels considered were U235 and U233, and both D2O and H2O moderated systems were studied. Critical fuel concentrations were calculated as functions of size, temperature, and thorium concentration. For 4- to 5 1/2-ft diameter spherical ThO2-D2O reactors fueled with U235, the minima in the U235/Th ratio curves occurred at about 200 gm Th/liter. The critical ratio obtained for a 5-ft diameter bare D2O reactor at 280°C increased from 0.08 to 0.10 g U235/g Th as a thorium concentration was increased from 200 to 400 gms per liter.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-12-017758
OSTI ID:
4286111
Report Number(s):
CF-58-7-76
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-58
Country of Publication:
United States
Language:
English

Similar Records

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CONFIGURATION
CRITICALITY
DENSITY
EQUATIONS
FUEL SLURRIES
HEAVY WATER MODERATOR
MASS
REACTOR CORE
REACTORS
SPHERES
TEMPERATURE
THORIUM
THORIUM OXIDES
URANIUM 233
URANIUM 235
WATER MODERATOR
Nuclear Criticality Safety Program (NCSP)
Criticality
Heavy Water Moderator
Mass
Critical Mass
Survey
Nuclear
Characteristics
Reactor Core
Thorium
Uranium
Concentration