International audienceNeutron flux monitoring system forms an integral part of the safety design of a Generation IV sodium cooled fast reactor system. During the initial design phase of a neutron flux monitoring system, one needs to explore various locations and configurations. Diverse possibilities of detector system installation should be studied for different locations in the reactor vessel in order to detect any perturbations in the core. In this paper, we investigate the possibility of placing fission chambers beyond the lateral neutron shield, ex-core but in-vessel and study the detectability of inadvertent control rod withdrawal with these fission chambers. A generic core design of a Generation IV, 1500 MWth French sodium-cooled fast...
International audienceMonitoring fuel integrity during sodium-cooled fast reactor operation becomes ...
Doctor of PhilosophyDepartment of Mechanical and Nuclear EngineeringDouglas S. McGregorAdvancements ...
The measurements of physical parameters of the TRIGA reactor and Nuclear power plant Krško (NEK) rea...
International audienceNeutron flux monitoring system forms an integral part of the safety design of ...
Safety and reliability are one of the key objectives for future Generation IV nuclear energy systems...
International audienceThe neutron flux monitoring system of the French GEN-IV sodium-cooled fast rea...
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given t...
The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on high...
ISBN: 978-0-89448-726-2International audienceFission chambers are the detector of choice for online,...
International audienceIn order to meet clean core challenges in Sodium-Cooled Fast Reactors (SFR), s...
Neutron transport analysis is used to evaluate the effects of neutron calibration source position, s...
The new reactor concepts proposed in the Generation IV International Forum require the development a...
The work presented here is concerned with the detection of flux irregularities in large pebble-bed h...
The focus in this thesis is to improve knowledge of the BWR related uncertainties void, channel bow,...
The Sodium cooled Fast Reactor (SFR) is one of the six reactor types selected by the Generation-IV i...
International audienceMonitoring fuel integrity during sodium-cooled fast reactor operation becomes ...
Doctor of PhilosophyDepartment of Mechanical and Nuclear EngineeringDouglas S. McGregorAdvancements ...
The measurements of physical parameters of the TRIGA reactor and Nuclear power plant Krško (NEK) rea...
International audienceNeutron flux monitoring system forms an integral part of the safety design of ...
Safety and reliability are one of the key objectives for future Generation IV nuclear energy systems...
International audienceThe neutron flux monitoring system of the French GEN-IV sodium-cooled fast rea...
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given t...
The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on high...
ISBN: 978-0-89448-726-2International audienceFission chambers are the detector of choice for online,...
International audienceIn order to meet clean core challenges in Sodium-Cooled Fast Reactors (SFR), s...
Neutron transport analysis is used to evaluate the effects of neutron calibration source position, s...
The new reactor concepts proposed in the Generation IV International Forum require the development a...
The work presented here is concerned with the detection of flux irregularities in large pebble-bed h...
The focus in this thesis is to improve knowledge of the BWR related uncertainties void, channel bow,...
The Sodium cooled Fast Reactor (SFR) is one of the six reactor types selected by the Generation-IV i...
International audienceMonitoring fuel integrity during sodium-cooled fast reactor operation becomes ...
Doctor of PhilosophyDepartment of Mechanical and Nuclear EngineeringDouglas S. McGregorAdvancements ...
The measurements of physical parameters of the TRIGA reactor and Nuclear power plant Krško (NEK) rea...