The MORSE code :
a multigroup neutron and gamma-ray Monte Carlo transport code /
E.A. Straker... [and others].

Description

Related Names

Cain, V.R.
Irving, D. C.
Stevens, P. N.
Straker, E. A.
United States. Defense Atomic Support Agency.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

Language(s)

English

Published

Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1970.

Subjects

Neutrons > Neutrons / Scattering.
Gamma rays > Gamma rays / Data processing.
Neutrons > Neutrons / Data processing.
Transport theory > Transport theory / Data processing.
Nuclear physics > Nuclear physics / Data processing.
Monte Carlo method > Monte Carlo method / Computer programs.
Neutron transport theory.

Summary

The MORSE code is a multipurpose neutron and gamma-ray transport Monte Carlo code. Through the use of multigroup cross sections, the solution of neutron, gamma-ray, or coupled neutron-gamma-ray problems may be obtained in either the forward or adjoint mode. Time dependence for both shielding and criticality problems is provided. General three-dimensional geometry, as well as specialized one-dimensional geometry descriptions, may be used with an albedo option available at any material surface. A detailed discussion of the relationship between forward and adjoint flux and collision densities, as well as a detailed description of the treatment of the angle of scattering, is given in the appendices. Logical flow charts for each subroutine add to the understanding of the code.

Note

Operated by Union Carbide Corporation for the U.S. Atomic Energy Commission.
"Note: This work partially funded by Defense Atomic Support Agency under subtask PEO8001."
"September 1970."

Physical Description

302 p. : ill. ; 27 cm.

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