RCP01; Monte Carlo neutron and photon transport. [CDC7600,6600; FORTRAN IV]

Technical Report ·

OSTI ID:6411634

Fowler, T B; Tobias, M L; Fox, J N; Lawler, B E; Koppel, J U; Triplett, J R; Lynn, L L; Waldman, L A; Goldberg, I; Greebler, P; Kelley, M D; Davis, R A; Keck, C E; Redfield, J A; Murphy,

RCP01 is a Monte Carlo program which estimates neutron capture rates and photon heating rates over the energy range important to the fission process, i.e., 10 Mev to 0 ev. There is a neutron eigenvalue capability as well as the usual fixed source capability. The geometry is modular comprising: (a) module zero, a set of concentric cylinders or spheres with axial material boundaries; (b) final modules, each a collection of rectangular or 60 degree parallelogram initial assemblies superimposed on module zero at arbitrary positions and angular orientations; (c) initial assemblies of rectangles and 60 degree parallelograms with internal structure determined by an overlay on a variable mesh; (d) optional use of doubly repetitive ''subcells'' containing arbitrary collections of non-intersecting elliptical surfaces within initial assemblies. Other geometric features include the geometry variation which provides trapezoidal and equilateral triangular final assemblies and composite final assemblies which are pairs of final assemblies, one arbitrarily positioned and oriented within the other. Edits of absorption, heating, and neutron production are produced, with corresponding uncertainties, for each material (composition) by nuclide by energy group.CDC7600,6600; FORTRAN IV with COMPASS equivalent routines for a selected few key subroutines.; SCOPE 1.1, SCOPE 2.1.5 (CDC7600), SCOPE 3.3, 3.4 (CDC6600); CDC7600 or CDC6600 with variable requirement of Large Core Memory (LCM) or Extended Core Storage (ECS). The sample problem requires approximately 106K (octal) words of central memory and 46K (octal) words of ECS on the CDC6600.

• Research Organization: Argonne National Lab., IL (USA)
• OSTI ID: 6411634
• Report Number(s): ANL/NESC-670R; ON: DE83048670
• Country of Publication: United States
• Language: English

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
COMPUTER CODES
CRITICALITY
KINETICS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
PHOTON TRANSPORT
R CODES
RADIATION TRANSPORT
REACTION KINETICS
THREE-DIMENSIONAL CALCULATIONS