Monte Carlo simulations of the pulsed thermal neutron flux in two-zone systems with Plexiglas – Using the MCNP code with a modified hydrogen-data library

Author:

Krynicka Ewa,Wiącek Urszula,Drozdowicz Krzysztof,Gabańska Barbara,Tracz Grzegorz

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference21 articles.

1. A pulsed method for measuring thermal diffusion parameters of non-moderating media;Demény;Nucl. Geophys.,1988

2. An isotopic neutron source method for measuring the thermal neutron absorption cross section of rocks using small samples;Kreft;Nucl. Geophys.,1989

3. Thermal neutron macroscopic absorption cross-section measurement applied for geophysics;Czubek;Progress Nucl. Energy,1996

4. Steady neutron source measurement method for Σa and Σs in geological samples;Sood;Appl. Radiat. Isot.,2000

5. Experimental detection of the hydrogen content in rock material by a pulsed neutron method;Drozdowicz;Nucl. Instr. and Meth. B,2006

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