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

E.J. Leshan | Zendy; D.L. Kavanagh | Zendy

Open Access

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

Author(s) -

E.J. Leshan,

D.L. Kavanagh

Publication year - 1960

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4020501

Subject(s) - diffusion theory , nuclear physics , diffusion , uranium 238 , physics , fission , neutron , neutron flux , xenon , isotope , nuclear data , nuclear engineering , thermodynamics , engineering

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 constaants 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. (auth

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