PHROG; multi-group constant and fast spectra calculations. [IBM360; FORTRAN IV]

Technical Report ·

OSTI ID:6343403

Curtis, R L; Grimesey, R A

PHROG generates energy dependent fast neutron spectra and associated multigroup cross section data suitable for use in diffusion and transport theory reactor design analysis. The solution utilizes 68 equal lethargy groups of cross section, source, and leakage data over an energy range extending from 10 MeV to 0.414 eV. These data are then coalesced into broad group form using the fluxes and currents as weighting functions.IBM360; FORTRAN IV; OS/360; 200K bytes memory and six I/O devices including card reader, printer, card punch, tape unit for cross section library, and 2 scratch units.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• OSTI ID: 6343403
• Report Number(s): ANL/NESC-520; ON: DE83048520
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
BARYONS
COMPUTER CODES
CROSS SECTIONS
DANCOFF CORRECTION
E CODES
ELEMENTARY PARTICLES
FAST NEUTRONS
FERMIONS
GROUP CONSTANTS
HADRONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON SPECTRA
NEUTRON TRANSPORT
NEUTRONS
NUCLEONS
P CODES
RADIATION TRANSPORT
RESONANCE
SPECTRA