Resonance neutron capture in a thick slab of depleted uranium.
Group cross section generating techniques to calculate neutron capture rates and spatial capture distribution in depleted thick U slab, using GAROL program
Lahti, G. P.↗
Engineering topics
Lahti, G. P.
Publications and source records attributed to Lahti, G. P..
OPEX 2 - A radiation shield optimization code
FORTRAN program for radiation shield optimization using steepest descent method
Lahti, G. P.↗
Comparison of small water-graphite nuclear rocket stages with chemical upper stages for unmanned missions
Small water-graphite nuclear rocket stages compared with chemical upper stages for use in unmanned spacecraft
Clark, M. R.↗
Fission neutron attenuation in lithium-6, natural lithium hydride, and tungsten
Discrete ordinate computation of fission spectrum neutron dose rate attenuation curve for lithium hydrides and tungsten
Lahti, G. P.↗
Preliminary considerations for fast-spectrum, liquid-metal cooled nuclear reactor program for space-power applications
Size and shield weight requirements calculated for fast-spectrum, liquid-metal cooled nuclear reactor for space power application
Lahti, G. P.↗
Some uses of discrete ordinates codes for shielding analysis at NASA, Lewis Research Center
Discrete ordinates codes used to determine secondary gamma sources in reactor assemblies and shields
Lahti, G. P.↗
MCFLARE, a Monte Carlo code to simulate solar flare events and estimate probable doses encountered on interplanetary missions
Computer program using Monte Carlo methods for simulating solar flares during interplanetary space flight
Karp, I. M.↗
QADHD point-kernel radiation shielding computer code to evaluate propellant heating and dose to crew during engine operation
Point-kernel radiation shielding computer program to evaluate propellant heating and dose to crew during engine operation
RADIATION DOSE↗