Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

A MONTE CARLO CALCULATION OF THE TRANSPORT OF NEUTRONS THROUGH IRON SLABS. Paper 13 of PAPERS FROM SEVENTH SEMIANNUAL SHIELDING INFORMATION MEETING, OCTOBER 14-15, 1959

Technical Report ·
OSTI ID:4092551

A Monte Carlo sampling is used to calculate the transmitted number current, number flux, dose, and the dose albedos of neutrons incident on an iron slab. A plane parallel source of monoenergetic neutrons with a number current density of 1 neutron/cm/sup 2/-sec is incident from a vacuum upon an iron slab of finite thickness. Transmission factors and linear buildup factors are computed for the above quantities. The dose transmission and the dose albedo are calculated for each of 120 equal solid angles. Gamma rays from inelastic scattering are recorded as a function of energy and penetration depth. (auth)

Research Organization:
Lockheed Aircraft Corp., Marietta, Ga.
NSA Number:
NSA-15-010332
OSTI ID:
4092551
Report Number(s):
TID-6302(Paper 13)
Country of Publication:
Country unknown/Code not available
Language:
English