RAFFLE V general purpose Monte Carlo code for neutron and gamma transport. Revision 1
Technical Report
·
OSTI ID:5526139
The RAFFLE V general-purpose Monte Carlo code is an extensively-modified version of the original RAFFLE code developed at INEL. This document describes the RAFFLE V code, emphasizing the modifications made since prior documentation. The major modifications implemented into the RAFFLE V code are: (1) implementation of the processed ENDF-B version V neutron data and an expansion of the energy range to include above-10-MeV reactions important in fusion devices; (2) incorporation of the Combinatorial Geometry subroutines developed by the Mathematical Applications Group Incorporated (MAGI) of White Plains, New York; (3) use of the Probability Table method in the unresolved resonance energy region so that neutron transport and flux shielding can be better represented; (4) the capability to perform gamma-ray transport calculations; (5) the inclusion of flux-at-a-point detectors; (6) the option to obtain microscopic reaction rates and generalized response functions by region or point; and (7) the capability to obtain time-dependent reaction rates and fluxes for fixed-source problems with no fission.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5526139
- Report Number(s):
- EGG-PHYS-6003-Rev.1; ON: DE84003847
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
654001 -- Radiation & Shielding Physics-- Radiation Physics
Shielding Calculations & Experiments
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BOLTZMANN EQUATION
COMPUTER CODES
COMPUTERS
DIFFERENTIAL EQUATIONS
EQUATIONS
FORTRAN
IBM COMPUTERS
MODIFICATIONS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
PARTIAL DIFFERENTIAL EQUATIONS
PHOTON TRANSPORT
PROGRAMMING LANGUAGES
R CODES
RADIATION TRANSPORT
Shielding Calculations & Experiments
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BOLTZMANN EQUATION
COMPUTER CODES
COMPUTERS
DIFFERENTIAL EQUATIONS
EQUATIONS
FORTRAN
IBM COMPUTERS
MODIFICATIONS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
PARTIAL DIFFERENTIAL EQUATIONS
PHOTON TRANSPORT
PROGRAMMING LANGUAGES
R CODES
RADIATION TRANSPORT