DMM: A Multigroup, Multiregion, One-Space-Dimensional Computer Program Using Neutron Diffusion Theory. Part I: The Theory (Final Report)

Technical Report · Sat Dec 31 04:00:00 EST 1960

DOI:https://doi.org/10.2172/4020501· OSTI ID:4020501

Leshan, Edward J. ^[1]; Kavanagh, Devereux L. ^[1]

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1. American-Standard, Mountain View, CA (United States). Advanced Technology Laboratories

DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Calculations of fission-produced xenon and samarium and time variation due to production and depletion of isotopes are an essential part of this program. 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. The present code is written for the Remington Rand 1103A. Operating instructions are presented in Part II of this report.

• Research Organization: American-Standard, Mountain View, CA (United States). Advanced Technology Laboratories
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC); US Air Force
• NSA Number: NSA-15-025118
• OSTI ID: 4020501
• Report Number(s): ATL-A-105
• 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
COMPUTERS
CRITICALITY
CROSS SECTIONS
Computers
Criticality
DIFFUSION
DISTRIBUTION
Diffusion
Distribution
FISSION PRODUCTS
Fission
GROUP THEORY
ISOTOPES
NEUTRON FLUX
NEUTRONS
Neutron Flux
Nuclear Criticality Safety Program (NCSP)
PROGRAMMING
REACTIVITY
SAMARIUM
Theory
XENON