MICRETE 4 : BASIC THEORY

Author: Stewart, J. D.
Published: Canada : [publisher not identified], 1971.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1971.
Physical Description: microfiche : negative ; 11 x 15 cm

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Report Numbers

AECL-4053

Other Subject(s)

COMPUTER PROGRAMS/MICRETE 4, for fast and thermal neutron flux distributions in reactors
COMPUTERS
DISTRIBUTION
FAST NEUTRONS
MATHEMATICS
N38190* -Power Reactor Development-Power Conversion Systems
NEUTRON FLUX
NEUTRONS, FAST/flux distribution in reactors, computer program calculation of.
NEUTRONS, THERMAL/flux distribution in reactors, computer program calculation of.
PROGRAMMING
REACTORS
REACTORS/neutron flux distribution in, computer program for fast and thermal
THERMAL NEUTRONS

Collection

U.S. Atomic Energy Commission depository collection.

Note

NSA number: NSA-26-006318
OSTI Identifier 4691204
Research organization: Atomic Energy of Canada Ltd., Chalk River (Ontario). Chalk River Nuclear Labs..

View MARC record | catkey: 37110642

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MICRETE 4 : BASIC THEORY

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