SHIELDING COMPUTER PROGRAM 14-0, REACTOR SHIELD ANALYSIS
Technical Report
·
OSTI ID:4801552
Shielding Computer Program 14-0 evaluates point-topoint attenuation functions and integrates over source regions to perform reactor-shield penetration calculations for neutrons and gamma rays. Neutron dose rates and gamma ray flux and dose and energy absorption rates can be computed for positions in and around complex reactor shields containing multiple sources described in a cylindrical coordinate system. In addition, the program can compute reactor- shield weight. Computation of any or all of these quantities in a single problem is optional. Enough physical and souree deseription capability is provided by the program that nuclear analysis of reactor-shield assemblies currently considered at ANPD should involve little uncertainty except that assoeiated with point-to-point attenuation functions and secondary souree distributions. A modification of the Albfert-Welton theory of neutron attenuation is used for fast neutron dose rate calculations. Combination of buildup factors by empirical expressions is used with exponential attenuation to compuie gamma ray doae rates. The program is coded for use on an IBM-704 having 32,768 magnetic eore memory locations. Magnetic tape units are used for the production package and output. No magnetic drum memory is required. (auth)
- Research Organization:
- General Electric Co. Aircraft Nuclear Propulsion Dept., Cincinnati
- DOE Contract Number:
- AT(11-1)-171
- NSA Number:
- NSA-16-011120
- OSTI ID:
- 4801552
- Report Number(s):
- DC 58-5-132
- Country of Publication:
- United States
- Language:
- English
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