MAC-A BULK SHIELDING CODE
The MAC Computer Code provides a method for calculating neutron and gamma attenuation through reactor shield assemblies. The code was tested by comparing calculations with experimental data on material obtained in the Hanford Bulk Shield Facility. The materials include iron-masonite, ferrophosphorus concrete, iron-serpentine concrete, and ordinary concrete. The cases involved total material thickness of 210 to 230 cm, and attenuation factors of about 10/ sup 12/ and 10/sup 10/ for neutrons and gammas, respectively. The calculations provided an excellent fit to the experimental data and generally agreed with measured flux values. The agreement was considered to be very satisfactory in view of the large thickness and attenuation factors involved. An over-all reduction in the amount of experimentation required to find an optimum shield material is achievable with the MAC code. Calculation of the shielding properties for new materials may be carried out in bulk shielding facilities and only the most promising tested. Agreement between calculation and experimental results obtained from the bulk shielding facilities geometry then permits calculation for other geometries with a high degree of confidence. (auth)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-16-019236
- OSTI ID:
- 4830276
- Report Number(s):
- HW-73381
- Country of Publication:
- United States
- Language:
- English
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