MOD-5: A Computer Code for Calculations of Neutron Time-Energy Distributions in the Slowing Down Region.

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Abstract:

The document provides users information for a computer code, MOD-5, which calculates the time and energy dependent evolution of the neutron density in homogeneous media following initiation of a pulsed neutron source of arbitrary energy distribution. The code is based on a discrete stochastic model of the neutron slowing down process developed by the author. Author

Author(s):
Williamson, Theodore J.
Author Organization(s):
NAVAL POSTGRADUATE SCHOOL MONTEREY CALIF
Descriptive Note:
Technical rept.,
Pagination:
0134

Security Markings

DOCUMENT & CONTEXTUAL SUMMARY

Distribution:
Approved For Public Release

RECORD

Collection: TR
Identifying Numbers
Report Number(s):
NPS-61WN71061A
 Subject Terms
Communities of Interest:
Energy and Power Technologies
Descriptor(s):
(*NEUTRON TRANSPORT THEORY, *COMPUTER PROGRAMS), MATHEMATICAL MODELS, STOCHASTIC PROCESSES, NUMERICAL ANALYSIS
Field(s)/Group(s):
Computer Programming and Software, Fission Reactor Physics, Nuclear Physics and Elementary Particle Physics
Keyword(s):
FORTRAN, FORTRAN 4 PROGRAMMING LANGUAGE
Report Date:
1971 Jun 01