In the 1980s, a series of critical experiments referred to as the Haut Taux de Combustion (HTC) experiments was conducted by the Institut de Radioprotection et de Surete Nucleaire (IRSN) at the experimental criticality facility in Valduc, France. The plutonium-to- uranium ratio and the isotopic compositions of both the uranium and plutonium used in the simulated fuel rods were designed to be similar to what would be found in a typical pressurized-water reactor fuel assembly that initially had an enrichment of 4.5 wt% {sup 235}U and was burned to 37,500 MWd/MTU. The fuel material also includes {sup 241}Am, which is present due to the decay of {sup 241}Pu. The HTC experiments include configurations designed to simulate fuel handling activitie...
The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation o...
As part of work to evaluate the potential benefits of using thorium in LWR fuel, a thorium fueled be...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
In the 1980s a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a ...
The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified ...
From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experime...
The completion of criticality experiments for mixtures of transuranic actinides (TRU–includes Np, Pu...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
This project represents a collaborative R&D programme in the field of HTR-related nuclear physics, w...
In the operation of a nuclear power plant, it is very important to determine the time evolution of m...
The completion of criticality experiments for mixtures of higher actinides (HA, includes neptunium, ...
Engineers from Argonne National Lab's Global Threat Reduction Initiative program and engineers from ...
Within the Generation IV International Forum (GIF), considerable efforts are devoted in Europe to re...
International audienceThis paper describes the experimental programs conducted in France by the Atom...
This report describes criticality benchmark experiments containing rhodium that were conducted as pa...
The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation o...
As part of work to evaluate the potential benefits of using thorium in LWR fuel, a thorium fueled be...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
In the 1980s a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a ...
The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified ...
From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experime...
The completion of criticality experiments for mixtures of transuranic actinides (TRU–includes Np, Pu...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
This project represents a collaborative R&D programme in the field of HTR-related nuclear physics, w...
In the operation of a nuclear power plant, it is very important to determine the time evolution of m...
The completion of criticality experiments for mixtures of higher actinides (HA, includes neptunium, ...
Engineers from Argonne National Lab's Global Threat Reduction Initiative program and engineers from ...
Within the Generation IV International Forum (GIF), considerable efforts are devoted in Europe to re...
International audienceThis paper describes the experimental programs conducted in France by the Atom...
This report describes criticality benchmark experiments containing rhodium that were conducted as pa...
The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation o...
As part of work to evaluate the potential benefits of using thorium in LWR fuel, a thorium fueled be...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...