SPIC-1--AN IBM-704 CODE TO CALCULATE THE NEUTRON DISTRIBUTION OUTSIDE A RIGHT-CIRCULAR CYLINDRICAL SOURCE
The SPIC-1 code calculates the fast-neutron dose rate or the thermal neutron flux at a point outside a right circular cylindrical source which is surrounded by cylindrical shell shields and is capped by plane slab shields. The fast neutron attenuation kennel is empirical and is in the form of a linear combination of single exponentials which has been fitted to the experimental fast- neutron dose rate distribution in pure water. Empirical neutron removal cross sections are used to represent the attenuation by shells of non-hydrogeneous materials located in the water. Typical computing and editing time for a 20- field-point-problem, in which there are 10 side and 10 top shields, is 6.5 minutes. The code requires an lBM-704 EDPM with a memory of 32,708 words. (auth)
- Research Organization:
- Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-14-002809
- OSTI ID:
- 4228264
- Report Number(s):
- WAPD-TM-196
- Country of Publication:
- United States
- Language:
- English
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