MOD5; stochastic model of neutron slowing-down. [IBM360; FORTRAN IV]

Technical Report ·

OSTI ID:6365032

Williamson, T J

MOD5 calculates the time- and energy-dependent evolution of the neutron density in homogeneous media following initiation of a) a monoenergetic source distributed over a finite time interval, or b) a source of arbitrary spectrum with a delta-function distribution in time. Effectively the code produces Green's function solutions to the slowing-down equation in discrete numerical form. Leakage is treated in the diffusion approximation. The program a) calculates spectra and energy moments at selected times following the burst of source neutrons, b) evaluates the time-dependent neutron density and slowing-down density at selected energies and computes moments of these densities, c) calculates time-dependent distributions of capture, leakage and first fission, and moments of these distributions, d) calculates steady-state central core neutron flux and leakage flux in detail and in group-averaged form, and e) calculates parameters such as keff.IBM360; FORTRAN IV; IBM360 CP-CMS; 175K bytes memory, normal input, output, program, and punch units, 6 cylinders of IBM2314 or equivalent direct-access storage.

• Research Organization: Naval Postgraduate School, Monterey, CA (USA)
• OSTI ID: 6365032
• Report Number(s): ANL/NESC-491; ON: DE83048491
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
M CODES
S CODES
NEUTRONS
SLOWING-DOWN
MULTIGROUP THEORY
NEUTRON TRANSPORT
SCATTERING
SPECTRA
STOCHASTIC PROCESSES
TIME DEPENDENCE
BARYONS
ELEMENTARY PARTICLES
FERMIONS
HADRONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEONS
RADIATION TRANSPORT
TRANSPORT THEORY
654003* - Radiation & Shielding Physics- Neutron Interactions with Matter