A Multigroup, Multiregion, One-Space Dimensional Program Using Neutron Diffusion Theory

Technical Report · Sat Dec 01 04:00:00 EST 1956

DOI:https://doi.org/10.2172/4360889· OSTI ID:4360889

Franklin, Joel ^[1]; Leshan, Edward J. ^[1]

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1. American Radiator and Standard Sanitary Corp., Redwood City, CA (United States)

DMM is a program using multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. As an essential part of this program are calculations of perpendicular buckling, fission produced xenon, and time variation, due to production and depletion of isotopes. The adjoint fluxes may also be computed and the program includes the calculation of the nuclear constants from fairly simple input combined with a library of cross sections. DMM is presently being coded for the Datatron, the Remington Rand 1103A, and the IBM 704.

• Research Organization: American Radiator and Standard Sanitary Corp., Redwood City, CA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• NSA Number: NSA-11-004075
• OSTI ID: 4360889
• Report Number(s): ASAE-4
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BUCKLING
Buckling
COMPUTERS
CONFIGURATION
CRITICALITY
CROSS SECTIONS
Criticality
DATATRON
DIFFUSION
Datatron
Diffusion Theory
EPITHERMAL NEUTRONS
FAST NEUTRONS
FISSION PRODUCTS
GROUP THEORY
IBM 704
MASS
MULTIPLICATION FACTORS
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
POISONING
PROGRAMMING
REACTIVITY
REACTOR CORE
REACTORS
Remington Rand 1103A
THERMAL NEUTRONS
TRANSPORT THEORY
XENON
ZONES