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Publications by D. O. Samson
Estimation of Fuel Burnup Rate for Core Conversion for the Nigeria Research Reactor-1 (NIRR-1) Fueled With 19.75% Enriched UO2 USING VENTURE PC Code
Physical Science International Journal
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Experimental Study on Reactivity Worth for Absorber Material in High Conversion Light Water Reactor Using FCA-HCLWR Core Fueled With Enriched Uranium.
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The Thermohydraulic Analysis of the Bandung Research Reactor Core With Plate Type Fuel Elements Using the CFD Code
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Effect of Temperature Difference and Control Rod Movement on Neutron Flux Distribution in Nigeria Research Reactor-1 Core
Recent Advances in Petrochemical Science
Large Core Code Evaluation Working Group Benchmark Problem Four: Neutronics and Burnup Analysis of a Large Heterogeneous Fast Reactor. Part 1. Analysis of Benchmark Results. [LMFBR]
Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel
VENTURE/PC Manual: A Multidimensional Multigroup Neutron Diffusion Code System
