CCC-0187 SAM-CE. (Abstract last modified 04-APR-2003)
1.
NAME OR DESIGNATION OF PROGRAM - SAM-CE. 2.
COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
CCC-0187/01 CDC 6600 CDC 6600
CCC-0187/02 IBM 370 series IBM 370 series
3.
NATURE OF PHYSICAL PROBLEM SOLVED - The SAM-CE system comprises two Monte Carlo codes, SAM-F and SAM-A. SAM-F supercedes the forward Monte Carlo code, SAM-C. 4.
METHOD OF SOLUTION - A special feature of SAM-CE is its use of the 'combinatorial geometry' technique which affords the user geometric capabilities exceeding those available with other commonly used geometric packages. 5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - Essentially no restrictions for neutron problems. For gamma-ray problems, only Compton scattering and absorption are treated. 6.
TYPICAL RUNNING TIME - Highly problem dependent. 7.
UNUSUAL FEATURES OF THE PROGRAM - 8.
RELATED AND AUXILIARY PROGRAMS - BCDEAN - translates element data tapes produced by SAM-X from binary into BCD mode and vice versa. 9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - On CDC 6600 - 210000 octal locations are needed. SAM-F and SAM-A are also operable on IBM/360. Several disc files and/or tapes are also needed. 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED - 14.
ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15.
NAME AND ESTABLISHMENT OF AUTHOR - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: ABSORPTION, COLLISIONS, CROSS SECTIONS, DOSES, GAMMA RADIATION, MONTE CARLO METHOD, NEUTRON TRANSPORT THEORY, SHIELDING, THREE-DIMENSIONAL, TIME DEPENDENCE
Program-name Package-ID Status
SAM-CE CCC-0187/01 Tested
SAM-CE CCC-0187/02 Tested
SAM-CE CCC-0187/03 Obsolete
SAM-CE CCC-0187/04 Obsolete
SAM-CE CCC-0187/05 Obsolete
SAM-A is an adjoint Monte Carlo code designed to calculate the response due to fields of primary and secondary gamma radiation.
The SAM-CE system is a FORTRAN Monte Carlo computer code designed to solve the time-dependent neutron and gamma-ray transport equations in complex three-dimensional geometries.
SAM-CE is applicable for forward neutron calculations and for forward as well as adjoint primary gamma-ray calculations. In addition, SAM-CE is applicable for the gamma-ray stage of the coupled neutron-secondary gamma ray problem, which may be solved in either the forward or the adjoint mode.
Time-dependent fluxes, and flux functionals such as dose, heating, count rates, etc., are calculated as functions of energy, time and position. Multiple scoring regions are permitted and these may be either finite volume regions or point detectors or both. Other scores of interest, e.g., collision and absorption densities, etc., are also made.
All nuclear interaction cross section data (derived from the ENDF for neutrons and from the UNC-format library for gamma-rays) are tabulated in point energy meshes. The energy meshes for neutrons are internally derived, based on built-in convergence criteria and user- supplied tolerances. Tabulated neutron data for each distinct nuclide are in unique and appropriate energy meshes. Both resolved and unresolved resonance parameters from ENDF data files are treated automatically, and extremely precise and detailed descriptions of cross section behaviour is permitted. Such treatment avoids the ambiguities usually associated with multi-group codes, which use flux-averaged cross sections based on assumed flux distributions which may or may not be appropriate.
By use of the 'band' feature of the code, which splits cross section data into two or more energy ranges to be treated one at a time, SAM-CE affords one the ability to consider many nuclides, in a given configuration, each being described in much detail.
SAM-CE also provides the user with the opportunity to employ energy, region and angular importance sampling.
CCC-0187/01: 24-MAR-1981 Tested at NEADB
CCC-0187/02: 10-OCT-1979 Tested at NEADB
CCC-0187/03: 01-JUN-1975 Obsolete
CCC-0187/04: 01-OCT-1978 Obsolete
CCC-0187/05: 04-APR-2003 Obsolete
- M. O. Cohen, et al.:
'SAM-CE - A Three-Dimensional Monte Carlo Code for the Solution of the Forward Neutron and Forward and Adjoint Gamma Ray Transport Equations'
MR-7021, DNA 2830F (November 1971).
CCC-0187/01:
- H. Lichtenstein et al.:
The SAM-CE Monte Carlo System for Radiation Transport and
Criticality Calculations in Complex Configurations (Revision 7.0)
EPRI CCM-8 (July 1979).
CCC-0187/02:
- Herbert A. Steinberg et al.:
SAM-CE - A Monte Carlo Code for Three Dimensional Neutron, Gamma
Ray and Electron Transport (Revision 5)
MR-7052-5 (May 1977).
CCC-0187/01: FORTRAN-IV
CCC-0187/02: FORTRAN-IV
Magi
3 Westchester Plaza
Elmsford, New York.
CCC-0187/01:
CCC0187_01.001 INFORMATION 2 records
CCC0187_01.002 SAMF SOURCE 15090 records
CCC0187_01.003 SAMF COMPLEX COMBINATORIAL GEOM 1232 records
CCC0187_01.004 SAMF JCL 20 records
CCC0187_01.005 SUBROUTINE ARG AND ARPREP 223 records
CCC0187_01.006 GAMMA RAY DATA PROCESSOR SOURCE (11/74) 297 records
CCC0187_01.007 SAMF INPUT DATA 89 records
CCC0187_01.008 SAMF OUTPUT 454 records
CCC0187_01.009 BCDEAN SOURCE 314 records
CCC0187_01.010 BCDEAN INPUT DATA 3 records
CCC0187_01.011 PHOTON CROSS SECTION 17548 records
CCC0187_01.012 BCDEAN JCL 19 records
CCC0187_01.013 BCDEAN OUTPUT 13 records
CCC0187_01.014 SAM-X SOURCE 10616 records
CCC0187_01.015 SAM-X INPUT DATA 9 records
CCC0187_01.016 FE CROSS SECTION ENDF/B-2 (11/74) 5293 records
CCC0187_01.017 SAM-X JCL 47 records
CCC0187_01.018 SAM-X OUTPUT 4042 records
CCC-0187/02:
CCC0187_02.001 BCDEAN SOURCE (F4,BCD) 314 records
CCC0187_02.002 INPUT EDT 17548 records
CCC0187_02.003 BCDEAN SAMPLE INPUT 3 records
CCC0187_02.004 BCDEAN SAMPLE OUTPUT 13 records
CCC0187_02.005 SAM-F SOURCE (F4,BCD) 9608 records
CCC0187_02.006 SAM-F OVERLAY CARDS 30 records
CCC0187_02.007 SAM-F SAMPLE INPUT 90 records
CCC0187_02.008 SAM-F SAMPLE OUTPUT 558 records
CCC0187_02.009 SAM-X SOURCE (F4,BCD) 10619 records
CCC0187_02.010 ICLOCK FUNCTION (DUMMY) 4 records
CCC0187_02.011 SAM-X OVERLAY CARDS 31 records
CCC0187_02.012 ENDF 5293 records
CCC0187_02.013 SAM-X SAMPLE INPUT 9 records
CCC0187_02.014 SAM-X SAMPLE OUTPUT 4042 records
- F. Space
Time Kinetics, Coupled Neutronics Hydrodynamics Thermodynamics
- J. Gamma Heating and Shield Design
Home - About Us - Work Areas - Data Bank - Publications - Press Room - List of acronyms - Search