Theory of Low Power Kinetics of Circulating Fuel Reactors with Several Groups of Delayed Neutrons

Technical Report · Fri Apr 01 04:00:00 EST 1955

DOI:https://doi.org/10.2172/4393291· OSTI ID:4393291

Fleck, Jr., J. A. ^[1]

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1. Brookhaven National Laboratory (BNL), Upton, NY (United States)

A method is described for computing reactor periods of circulating fuel reactors by finding the eigenvalues of a system of differential equations. The method accommodates two energy groups of neutrons and five groups of delayed neutrons. Approximate inhour equations are also derived for flat and sinusoidal fluxes and compared with the eigenvalue method. Discrepancies are largely attributable to differences in the delayed neutron spatial distribution.

• 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: AC02-76CH00016
• NSA Number: NSA-09-005493
• OSTI ID: 4393291
• Report Number(s): BNL-334
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Analysis
Circulating Fuel Reactors
Criticality
DELAYED NEUTRONS
DIFFERENTIAL EQUATIONS
DISTRIBUTION
Distribution
ERRORS
Equations
Errors
FUEL SLURRIES
FUEL SOLUTIONS
FUEL SUSPENSIONS
GROUP THEORY
LIQUID METAL FUEL
NEUTRON FLUX
NEUTRONS
Nuclear Criticality Safety Program (NCSP)
REACTIVITY
REACTOR KINETICS
REACTORS
Safety