Abstracts and Available Papers Presented at the 2004 International RERTR Meeting
MONTE CARLO NEUTRON TRANSPORT SIMULATION OF THE GHANA
RESEARCH REACTOR-1
S. Anim-Sampong, B.T. Maakuu, E.H.K. Akaho
Department of Nuclear Engineering & Materials Science
National Nuclear Research Institute
Ghana Atomic Energy Commission
P.O. Box LG 80, Legon, Accra, Ghana
ABSTRACT
Stochastic Monte Carlo neutron particle transport
methods have been applied to successfully model in 3-D,
the HEU-fueled Ghana Research Reactor-1 (GHARR-1), a
commercial version of the Miniature Neutron Source
Reactor (MNSR) using the MCNP version 4c3 particle
transport code. The preliminary multigroup neutronic
criticality calculations yielded a keff=1.00449 with a
corresponding cold clean excess reactivity of 4.47mk
(447pcm) compared with experimental values of keff=1.00402
and excess reactivity of 4.00mk (400pcm). The Monte
Carlo simulations also show comparable results in the
neutron fluxes in the HEU core and some regions of
interest. The observed trends in the radial and axial
flux distributions in the core, beryllium annular
reflector and the water region in the top shim reflector
tray were reproduced, indicating consistency of the
results, accuracy of the model, precision of the MCNP
transport code and the comparability of the Monte Carlo
simulations. The results further illustrate the close
agreement between stochastic transport theory and the
experimental measurements conducted during off-site zero
power cold tests.
Contact: Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161
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