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Actions for GENERALIZED, FINITE-DIFFERENCED, DIFFUSION EQUATION FOR NEUTRON-TRANSPORT COMPUTATIONS
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GENERALIZED, FINITE-DIFFERENCED, DIFFUSION EQUATION FOR NEUTRON-TRANSPORT COMPUTATIONS
Author
Alcouffe, R. E.
Published
United States : [publisher not identified], 1972.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1972.
Physical Description
microfiche : negative ; 11 x 15 cm
Full Text available online
Availability
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Report Numbers
LA-4938
Other Subject(s)
Mathematics
N78810 -reactor physics & core engineering-physics
Neutron transport theory
Neutrons
Neutrons/transport in reactors, finite differenced diffusion equations for, (t).
Reactors
Reactors/neutron transport in, finite differenced diffusion equations for, (t).
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: W-7405-ENG-36
NSA number: NSA-26-050010
OSTI Identifier 4635758
Research organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States).
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