A novel concept to detect pin-diversion from spent fuel assembly is proposed and described. The instrument will use multiple tiny neutron and gamma detectors in a form of cluster (detector cluster) and high precision driving system to collect radiation signatures inside pressurized water reactor (PWR) assembly. In order to validate our concept, a Monte Carlo study was done using a Monte Carlo code MCNP5. MONTEBURNS, a computational tool that links MCNP and ORIGEN, was used to produce accurate PWR spent fuel isotopic compositions. Monte Carlo simulations, using realistic fuel geometry and actual fuel material information, were performed to study radiation field inside a PWR spent fuel assembly. The preliminary Monte Carlo simulation study sh...
There are a variety of motivations for quantifying Pu in spent (used) fuel assemblies by means of no...
This final thesis project aims to define the main characteristics of an innovative out-core system t...
Access restricted to the OSU CommunityThe research presented here focuses on spent nuclear fuel asse...
The International Atomic Energy Agency (IAEA) has the responsibility to carry out independent inspec...
A technical safeguards challenge has remained for decades for the IAEA to identify possible diversio...
This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activatio...
The Passive Neutron Albedo Reactivity (PNAR) Ratio is proportional to the net neutron multiplication...
The verification of spent fuel assemblies is among the activities conducted during a safeguards insp...
A simulation-based study concerning three non-destructive approaches by which water in spent nuclear...
A measurement plan and preliminary Monte Carlo simulations are presented for the investigation of we...
There are a variety of reasons for quantifying plutonium (Pu) in spent fuel such as independently ve...
Over 80 per cent of the material placed under safeguards today is in the form of spent fuel and one ...
ii There has been a strong international interest in using pyroprocessing to close the fast nuclear ...
International audienceThe French Alternative Energies and Atomic Energy Commission (CEA) is conducti...
Recent attention to nuclear safeguards has stepped up the need for additional non proliferation safe...
There are a variety of motivations for quantifying Pu in spent (used) fuel assemblies by means of no...
This final thesis project aims to define the main characteristics of an innovative out-core system t...
Access restricted to the OSU CommunityThe research presented here focuses on spent nuclear fuel asse...
The International Atomic Energy Agency (IAEA) has the responsibility to carry out independent inspec...
A technical safeguards challenge has remained for decades for the IAEA to identify possible diversio...
This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activatio...
The Passive Neutron Albedo Reactivity (PNAR) Ratio is proportional to the net neutron multiplication...
The verification of spent fuel assemblies is among the activities conducted during a safeguards insp...
A simulation-based study concerning three non-destructive approaches by which water in spent nuclear...
A measurement plan and preliminary Monte Carlo simulations are presented for the investigation of we...
There are a variety of reasons for quantifying plutonium (Pu) in spent fuel such as independently ve...
Over 80 per cent of the material placed under safeguards today is in the form of spent fuel and one ...
ii There has been a strong international interest in using pyroprocessing to close the fast nuclear ...
International audienceThe French Alternative Energies and Atomic Energy Commission (CEA) is conducti...
Recent attention to nuclear safeguards has stepped up the need for additional non proliferation safe...
There are a variety of motivations for quantifying Pu in spent (used) fuel assemblies by means of no...
This final thesis project aims to define the main characteristics of an innovative out-core system t...
Access restricted to the OSU CommunityThe research presented here focuses on spent nuclear fuel asse...