Some Calculations Of The Fast Neutron Distribution In Ordinary Concrete From Point And Plane Isotropic Fission Sources
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Protection Against Neutron Radiation
| Author | : National Council on Radiation Protection and Measurements |
| Publisher | : |
| Total Pages | : 168 |
| Release | : 1971 |
| Genre | : Science |
| ISBN | : |
Reports Received by Division of Technical Information Extension
| Author | : U.S. Atomic Energy Commission. Division of Technical Information |
| Publisher | : |
| Total Pages | : 414 |
| Release | : |
| Genre | : Nuclear energy |
| ISBN | : |
Publications, Reports, and Papers for 1965 from Oak Ridge National Laboratory
| Author | : K.O. Johnsson |
| Publisher | : |
| Total Pages | : 356 |
| Release | : 1966 |
| Genre | : Technical reports |
| ISBN | : |
Neutron Physics Division Annual Progress Report for Period Ending ...
| Author | : Oak Ridge National Laboratory. Neutron Physics Division |
| Publisher | : |
| Total Pages | : 110 |
| Release | : 1964 |
| Genre | : Nuclear physics |
| ISBN | : |
Reactor Shielding for Nuclear Engineers
| Author | : Norman Morris Schaeffer |
| Publisher | : |
| Total Pages | : 804 |
| Release | : 1973 |
| Genre | : Technology & Engineering |
| ISBN | : |
Monte Carlo Calculations of the Penetration of Normally Incident Neutron Beams Through Concrete
| Author | : F. H. Clark |
| Publisher | : |
| Total Pages | : 24 |
| Release | : 1967 |
| Genre | : |
| ISBN | : |
The 05R Monte Carlo code (See ORNL-3622, NASA N65-17892) was adapted to calculate fast-neutron doses within and outside of concrete slab shields. Such calculations were performed for a variety of shield thicknesses (0 to 180 cm) and for various monoenergetic sources from 0.7 to 14 MeV. The concrete chosen is ordinary concrete with approximately 6% water content. Results are plotted as tissue kerma versus penetration distance for each source energy. The source is in each case a broad normally incident beam. (Author).
