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Uso del código MCNP para el transporte de neutrones térmicos en láminas de plata
(LimaPE, 2002-06)
El presente trabajo consistió en usar el código MCNP en la transmisión de neutrones en láminas de plata de espesor variable. Con fines prácticos, se asumió que el haz emergente de neutrones de la Columna Térmica, Posición ...
Nuclear reactor simulator in real time
(LimaPE, 2002-06)
Numerical methods are present to solve space-independent transport equations for 6 delayed neutron groups and the isotopic evolution of poisons produced in a reactor, as well as their implementation in the development of ...
Small Plasma Focus as Neutron Pulsed Source For Nucleids Identification
(Amer Inst Physics, 2013-10)
In this paper, we present preliminary results on the feasibility of employing a low energy (2 kJ, 31 kV) plasma focus device as a portable source of pulsed neutron beams (2.45 MeV) generated by nuclear fusion reactions ...