Search Results - "Sogbadji, R B M"

The design of a multisource americium–beryllium (Am–Be) neutron irradiation facility using MCNP for the neutronic performance calculation by Sogbadji, R.B.M., Abrefah, R.G., Nyarko, B.J.B., Akaho, E.H.K., Odoi, H.C., Attakorah-Birinkorang, S.

“…The americium–beryllium neutron irradiation facility at the National Nuclear Research Institute (NNRI), Ghana, was re-designed with four 20Ci sources using…”
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Characterization of low power research reactor neutrons for the validation of k(0)-INAA standardization based on k(0)-IAEA software by Baidoo, I K, Nyarko, B J B, Akaho, E H K, Dampare, S B, Sogbadji, R B M, Poku, L O

“…Channel Bsite2 of Ghana research reactor-1 has been characterized for k0-INAA application. Cadmium ratio and bare multi-monitor were used to determine flux…”
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Comparison of the effects of cadmium-shielded and boron carbide-shielded irradiation channel of the Ghana Research Reactor-1 by Abrefah, R.G., Sogbadji, R.B.M., Ampomah-Amoako, E., Birikorang, S.A., Odoi, H.C., Nyarko, B.J.B.

“…The MCNP model for the Ghana Research Reactor-1 (GHARR-1) was redesigned to incorporate cadmium-shielded irradiation channel as well as boron carbide-shielded…”
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Design of boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP by Abrefah, R.G., Sogbadji, R.B.M, Ampomah-Amoako, E., Birikorang, S.A., Odoi, H.C., Nyarko, B.J.B

“…The MCNP model for the Ghana Research Reactor-1 was redesigned to incorporate a boron carbide-shielded irradiation channel in one of the outer irradiation…”
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Investigative studies on effect of reflector thickness on the performance of low enriched uranium-fueled miniature neutron source reactors by Odoi, H.C., Akaho, E.H.K., Anim-Sampong, S., Jonah, S.A., Nyarko, B.J.B., Abrefah, R.G., Ampomah-Amoako, E., Sogbadji, R.B.M., Lawson, I., Birinkorang, S.A., Ibrahim, Y.V., Boffie, J.

“…► Evaluation of reflector thickness required to compensate for the decrease in neutron flux due to conversion of reactor core from HEU to LEU. ► Determination…”
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Design of epicadmium-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP by Abrefah, R.G., Sogbadji, R.B.M., Ampomah-Amoako, E., Birikorang, S.A., Odoi, H.C., Nyarko, B.J.B.

“…The MCNP model for the Ghana Research Reactor-1 was redesigned to incorporate an epicadmium-shielded irradiation channel in one of the outer irradiation…”
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Measurement of neutron flux distribution in the irradiation channel in the Ghana Research Reactor-1 using Monte Carlo method by Abrefah, R.G., Anim-Sampong, S., Nyarko, B.J.B., Akaho, E.H.K., Sogbadji, R.B.M.

“…The Monte Carlo method was used to determine the neutron fluxes in the irradiation channels of the Ghana Research Reactor-1. The MCNP5 code was used for this…”
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Ground deposition assessment of radionuclides following a hypothetical release from Ghana Research Reactor-1 (GHARR-1) using atmospheric dispersion model by Birikorang, S.A., Abrefah, R.G., Sogbadji, R.B.M., Nyarko, B.J.B., Fletcher, J.J., Akaho, E.H.K.

“…With the sustained development in computer technology, the possibilities of code capabilities have been enlarged substantially. Advanced safety evaluations and…”
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Neutron flux distribution in the irradiation channels of Am–Be neutron source irradiation facility by Asamoah, M., Nyarko, B.J.B., Fletcher, J.J., Sogbadji, R.B.M., Yamoah, S., Agbemava, S.E., Mensimah, E.

“…► We modeled Am–Be neutron source using MCNP-5. ► We estimated the neutron flux distribution in irradiation sites. ► The neutron fluxes peak at the center of…”
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Determination of thermal neutron cross-section and resonance integral for the 75As (n, γ) 76As reaction by activation method using 55Mn (n, γ) 56Mn as a monitor by Sogbadji, R.B.M., Nyarko, B.J.B., Akaho, E.H.K., Abrefah, R.G.

“…Nuclear constants for use in reactor activation analysis especially (n, γ) cross-sections and absolute gamma intensities, are known to show a rather large…”
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Axial and radial distribution of thermal and epithermal neutron fluxes in irradiation channels of the Ghana Research Reactor-1 using foil activation analysis by Abrefah, R.G., Nyarko, B.J.B., Akaho, E.H.K., Sampong, S. Anim, Sogbadji, R.B.M.

“…The experimental method (foil activation) was used to determine the neutron fluxes in two outer irradiation channels of the Ghana Research Reactor-1. In the…”
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Thermal neutron cross section determination of short-to-medium lived nuclides using a 20 Ci Am–Be neutron source by Agbemava, S.E., Nyarko, B.J.B., Fletcher, J.J., Sogbadji, R.B.M., Mensimah, E., Asamoah, M.

“…► Am–Be neutron source was used to measure cross sections using activation method. ► 55Mn(n,γ) 56Mn was used as the reference reaction for the measurement. ►…”
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Neutron energy spectrum flux profile of Ghana’s miniature neutron source reactor core by Sogbadji, R.B.M., Abrefah, R.G., Ampomah-Amoako, E., Agbemava, S.E., Nyarko, B.J.B.

“…► The total neutron flux spectrum of the compact core of Ghana’s miniature neutron source reactor was studied. ► Using 20,484 energy grids, the thermal,…”
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