SNAP PROGRAMS. M-1 MONTE CARLO RADIOISOTOPE SHIELDING CODE. Final Report
The M-1 code is a Monte Carlo code that applies to cylindrical geometry when solving for the flux from a pre specified radiation source. The source is a gamma and beta emitter and the solution is for the flux of each energy group and of each region of interest in regard to the emitter. A region is a volume of the system bounded by two planes perpendicular to the axis of symmetry and two cylinders (one cylinder if the region includes the axis of symmetry). The code can be used to solve for a maximum of 30 energy groups and 280 regions. The M-1 is coded in Fortran for a 32,000-word 7090 and requires that the energy intervals be prespecified as well as a complete description of the geometry of the system. A specification of materials in the system must also be given. The number of particles to be followed must be specified by the user. Since the technique of splitting can be employed here and so that splitting can occur, a description of the manner in which the system is divided (geometrically) must also be given by the user. A detailed description of the input required by the code is included. The dose per unit volume due to bremsstrahlung gammas for each prespecified region, and due to nonbremsstrahlung gammas for each prespecified region can be computed by the code. The total dose per unit volume for each prespecified region and the number of mean free paths traveled per second in each prespecified region for each energy group can also be computed along with the gamma flux for each prespecified region and for each energy group and the region volume associated with these parameters. (auth)
- Research Organization:
- Martin Co. Nuclear Div., Baltimore
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(30-3)-217
- NSA Number:
- NSA-16-027548
- OSTI ID:
- 4804070
- Report Number(s):
- MND-P-2726
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
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