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Papers by Ayodeji Alajo

Transactions of the American Nuclear Society, 2019

Flowchart representation of the dissertation ….…………………………… 2 Energy dependent radiative capture c... more Flowchart representation of the dissertation ….…………………………… 2 Energy dependent radiative capture cross sections of 90 Sr..…..…………… 3 Transformation path for strontium isotopes in transmutation scenario …... 4 Energy dependent radiative capture cross sections of 93 Zr ……….………. 5 Transformation path for zirconium isotopes in transmutation scenario …… 6 Energy dependent radiative capture cross sections of 99 Tc ………………...

This paper is focused on feasible autonomous control strategies for Generation IV Very High Tempe... more This paper is focused on feasible autonomous control strategies for Generation IV Very High Temperature Reactors (VHTR)-based systems for hydrogen production. Various burnable poison distributions and fuel compositions are considered. In particular, utilization of TRUs in VHTRs is explored as the core self-stabilization approach. Both direct cycle and indirect cycle energy conversion approaches are discussed. It is assumed that small-scale VHTRs may be considered for international deployment as grid-appropriate variable-scale self-contained systems addressing emerging demands for hydrogen. A Monte Carlo-deterministic analysis methodology has been implemented for coupled design studies of VHTRs with TRUs using the ORNL SCALE 5.1 code system. The developed modeling approach provides an exactgeometry 3D representation of the VHTR core details properly capturing VHTR physics. The discussed studies are being performed within the scope of the U.S. DOE NERI project on utilization of higher...

Iterative CT reconstruction from few projections for the nondestructive post irradiation examinat... more Iterative CT reconstruction from few projections for the nondestructive post irradiation examination of nuclear fuel assemblies

Transactions of the American Nuclear Society, 2013

Transactions of the American Nuclear Society, 2017

Minor actinides represent the long-term radiotoxicity of nuclear wastes. As one of their potentia... more Minor actinides represent the long-term radiotoxicity of nuclear wastes. As one of their potential incineration options, partitioning and transmutation in fission reactors are seriously considered worldwide. If implemented, these technologies could also be a source of nuclear fuel materials required for sustainability of nuclear energy. The objective of the U.S. DOE NERI Project is to assess the possibility, advantages and limitations of achieving ultra-long life VHTR (Very High Temperature Reactor) configurations by utilizing minor actinides as a fuel component. The analysis takes into consideration and compares capabilities of pebble-bed and prismatic core designs with advanced actinide fuels to approach the reactor lifetime long operation without intermediate refueling. This paper discusses the up-to-date research efforts. Whole-core/system 3D models with multi-heterogeneity treatments and property databases of actinide compounds are developed together with relevant benchmark pro...

Transactions of the American Nuclear Society, 2006

This paper is based upon work supported by the U.S. Department of Energy under Award Number DE-FC... more This paper is based upon work supported by the U.S. Department of Energy under Award Number DE-FC07-05ID14655 (05-094).

Transactions of the American Nuclear Society, 2012

Partitioning and transmutation of minor actinides are expected to have a positive impact on the f... more Partitioning and transmutation of minor actinides are expected to have a positive impact on the future of nuclear technology. Their deployment would lead to incineration of hazardous nuclides and could potentially provide additional fuel supply. The U.S. DOE NERI Project assesses the possibility, advantages and limitations of involving minor actinides as a fuel component. The analysis takes into consideration and compares capabilities of actinide-fueled VHTRs with pebble-bed and prismatic cores to approach a reactor lifetime long operation without intermediate refueling. A hybrid Monte Carlo-deterministic methodology has been adopted for coupled neutronics-thermal hydraulics design studies of VHTRs. Within the computational scheme, the key technical issues are being addressed and resolved by implementing efficient automated modeling procedures and sequences, combining Monte Carlo and deterministic approaches, developing and applying realistic 3D coupled neutronics-thermal-hydraulics...

Transactions of the American Nuclear Society, 2019

Flowchart representation of the dissertation ….…………………………… 2 Energy dependent radiative capture c... more Flowchart representation of the dissertation ….…………………………… 2 Energy dependent radiative capture cross sections of 90 Sr..…..…………… 3 Transformation path for strontium isotopes in transmutation scenario …... 4 Energy dependent radiative capture cross sections of 93 Zr ……….………. 5 Transformation path for zirconium isotopes in transmutation scenario …… 6 Energy dependent radiative capture cross sections of 99 Tc ………………...

This paper is focused on feasible autonomous control strategies for Generation IV Very High Tempe... more This paper is focused on feasible autonomous control strategies for Generation IV Very High Temperature Reactors (VHTR)-based systems for hydrogen production. Various burnable poison distributions and fuel compositions are considered. In particular, utilization of TRUs in VHTRs is explored as the core self-stabilization approach. Both direct cycle and indirect cycle energy conversion approaches are discussed. It is assumed that small-scale VHTRs may be considered for international deployment as grid-appropriate variable-scale self-contained systems addressing emerging demands for hydrogen. A Monte Carlo-deterministic analysis methodology has been implemented for coupled design studies of VHTRs with TRUs using the ORNL SCALE 5.1 code system. The developed modeling approach provides an exactgeometry 3D representation of the VHTR core details properly capturing VHTR physics. The discussed studies are being performed within the scope of the U.S. DOE NERI project on utilization of higher...

Iterative CT reconstruction from few projections for the nondestructive post irradiation examinat... more Iterative CT reconstruction from few projections for the nondestructive post irradiation examination of nuclear fuel assemblies

Transactions of the American Nuclear Society, 2013

Transactions of the American Nuclear Society, 2017

Minor actinides represent the long-term radiotoxicity of nuclear wastes. As one of their potentia... more Minor actinides represent the long-term radiotoxicity of nuclear wastes. As one of their potential incineration options, partitioning and transmutation in fission reactors are seriously considered worldwide. If implemented, these technologies could also be a source of nuclear fuel materials required for sustainability of nuclear energy. The objective of the U.S. DOE NERI Project is to assess the possibility, advantages and limitations of achieving ultra-long life VHTR (Very High Temperature Reactor) configurations by utilizing minor actinides as a fuel component. The analysis takes into consideration and compares capabilities of pebble-bed and prismatic core designs with advanced actinide fuels to approach the reactor lifetime long operation without intermediate refueling. This paper discusses the up-to-date research efforts. Whole-core/system 3D models with multi-heterogeneity treatments and property databases of actinide compounds are developed together with relevant benchmark pro...

Transactions of the American Nuclear Society, 2006

This paper is based upon work supported by the U.S. Department of Energy under Award Number DE-FC... more This paper is based upon work supported by the U.S. Department of Energy under Award Number DE-FC07-05ID14655 (05-094).

Transactions of the American Nuclear Society, 2012

Partitioning and transmutation of minor actinides are expected to have a positive impact on the f... more Partitioning and transmutation of minor actinides are expected to have a positive impact on the future of nuclear technology. Their deployment would lead to incineration of hazardous nuclides and could potentially provide additional fuel supply. The U.S. DOE NERI Project assesses the possibility, advantages and limitations of involving minor actinides as a fuel component. The analysis takes into consideration and compares capabilities of actinide-fueled VHTRs with pebble-bed and prismatic cores to approach a reactor lifetime long operation without intermediate refueling. A hybrid Monte Carlo-deterministic methodology has been adopted for coupled neutronics-thermal hydraulics design studies of VHTRs. Within the computational scheme, the key technical issues are being addressed and resolved by implementing efficient automated modeling procedures and sequences, combining Monte Carlo and deterministic approaches, developing and applying realistic 3D coupled neutronics-thermal-hydraulics...

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