last modified: 02-APR-1987 | catalog | categories | new | search |

IAEA0837 SAMSY.

SAMSY, Neutron and Gamma Dose Rates and Heat Source for Multilayer Shields

top ]
1. NAME OR DESIGNATION OF PROGRAM:  SAMSY - Shielding Analysis Modular  System.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
SAMSY IAEA0837/01 Tested 02-APR-1987

Machines used:

Package ID Orig. computer Test computer
IAEA0837/01 CDC CYBER 173 CDC CYBER 740
top ]
3. DESCRIPTION OF PROBLEM OR FUNCTION

The SAMSY code calculates multigroup neutron fluxes and dose rate, multigroup gamma ray dose rates and internal heat sources, as a function of distance through large multilayer reactor shields. I D geometries: plane, spheri- cal, cylindrical.
top ]
4. METHOD OF SOLUTION

The code is based on Spiney method for neutron  field analysis and on build-up factor method for gamma fields, with  two optional approaches to build-up factors evaluation; the first is based on single layer build-up factor conception as in the well-  known MAC-RAD code, and the second on the modified Harima-Nishiwaki  formula for build-up factors in multilayered media.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  26 neutron group, 7 gamma group, 1200 mesh-points.
top ]
6. TYPICAL RUNNING TIME:  About 5 minutes for 1200 mesh points on CDC CYBER 73.
IAEA0837/01
NEA-DB executed the test case included in this package  on a CDC CYBER 740 computer in 161 seconds of CPU time.
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

SAMSY is a complete system with its own data library RUSLIB (26 neutron group, 7 gamma group constants for 32 elements) attached to the program.
top ]
9. STATUS
Package ID Status date Status
IAEA0837/01 02-APR-1987 Tested at NEADB
top ]
10. REFERENCES
IAEA0837/01, included references:
- L. Szymendera, K. Wincel, L. Sobolewska et al ;
"SAMSY: A One-Dimensional Improved Shielding Code
User's Manual"
INR 1691 (1977)
- K.Wincel, L.Szymendera and I.Sobolewska ;
"Some Practical Application of Gamma Ray Build-Up
Factors for Multilayered Media"
INR 1690 (1977)
- I. Sobolewska, L.Szymendera, K.Wincel;
"A Modified harima-Nishiwaki Formula for Gamma Ray
Build-Up Factors in Multilayered Media"
INR 1689 (1977)
top ]
11. MACHINE REQUIREMENTS

    - 127500 octal high speed memory
    - 30 scratch files and INPUT, OUTPUT files on discs memory
    - Printer
IAEA0837/01
134,400 (octal) words of CM were required for running the test case on an CDC CYBER 740.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0837/01 FORTRAN-IV
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  Scope 3.4.
IAEA0837/01
NOS2.5.1 664/665 (CDC CYBER 740).
top ]
14. OTHER PROGRAMMMING OR OPERATING INFORMATION OR RESTRICTIONS

The
code has an overlay structure consisting of 7 overlays.
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

          K. Wincel, I. Sobolewski, D. Kordyasz, A. Polanski
          Institute of Nuclear Research
          Radiation Shielding Group 1977
          Warsaw
          Poland.
top ]
16. MATERIAL AVAILABLE
IAEA0837/01
File name File description Records
IAEA0837_01.001 Information file 64
IAEA0837_01.002 JCL control information 17
IAEA0837_01.003 SAMSY source program 2897
IAEA0837_01.004 QUAD and auxiliary subroutine 1060
IAEA0837_01.005 SAMSY sample problem input 37
IAEA0837_01.006 Data Library 1319
IAEA0837_01.007 SAMSY sample problem output 2210
IAEA0837_01.008 SAMSY original sample problem output 2210
top ]
17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: buildup, dose rates, gamma radiation, multigroup, neutron flux, one-dimensional, shielding.