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Exponential Experiments with Graphite Lattices Containing Multirod Slightly Enriched Uranium Fuel Clusters

Technical Report ·
DOI:https://doi.org/10.2172/4260106· OSTI ID:4260106
 [1];  [1];  [1]
  1. North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
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Studies of 13 exponential experiments with graphite moderated lattices containing multirod fuel clusters are presented. The bucklings and detailed intracell flux distributions were measured for each lattice. Average flux values for each material of the unit cell are given. The theoretical analysis yields a value of the effective resonance integral and of the resonance neutron inverse diffusion length in the moderator, which can be used in 2-group sodium graphite reactor calculations. There is evidence that neutron spectral hardening corrections are important, but a crude treatment of this effect did not improve the fit to the experimental measurements. The calculations are presented in detail, and various lattice parameters are tabulated.
Research Organization:
North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
Sponsoring Organization:
US Atomic Energy Commission (AEC); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AT-11-1-GEN-8
NSA Number:
NSA-13-007623
OSTI ID:
4260106
Report Number(s):
NAA-SR--3096
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
BUCKLING
CONFIGURATION
CRITICAL ASSEMBLIES
CRITICALITY
CRITICALITY STUDIES
Criticality Studies
DIFFUSION LENGTH
DISTRIBUTION
ERRORS
EXPONENTIAL PILES
FUEL ELEMENTS
GRAPHITE MODERATOR
GROUP THEORY
HARDENING
MATHEMATICS
MEASURED VALUES
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
REACTOR CORE
REACTORS
RESONANCE ESCAPE PROBABILITY
RODS
SODIUM
SPECTRAL SHIFT
TABLES
URANIUM 232