Flux Distribution for a Finite Cylindrical Bare Homogeneous Thermal Reactor with a Partially Inserted Control Rod

Technical Report · Mon Jul 01 00:00:00 EDT 1957

DOI:https://doi.org/10.2172/4368425· OSTI ID:4368425

Betinis, E. J. ^[1]

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1. North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.

One-group diffusion theory is employed to determine the flux for a large but finite cylindrical bare homogeneous reactor with a control rod inserted partially along the axis of the reactor. A critical equation is derived for the buckling.

• 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)
• NSA Number: NSA-11-010288
• OSTI ID: 4368425
• Report Number(s): NAA-SR--1963
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
BUCKLING
CONFIGURATION
CONTROL ELEMENTS
CRITICALITY
CYLINDERS
DIFFERENTIAL EQUATIONS
DIFFUSION
DISTRIBUTION
ERRORS
GROUP THEORY
HOMOGENEOUS REACTORS
LATTICES
MATHEMATICS
MECHANICS
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PHYSICS
REACTOR CORE
REACTORS
STATISTICS
THERMAL NEUTRONS