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Future nuclear power plants like the very high temperature reactor or the gas cooled fast reactor need materials able to comply with extreme operating conditions (temperature, cooling gas, radiation). Advanced materials like oxide dispersion strengthened ( ...
The shift toward low-enrichment uranium (LEU) fuel for gas-cooled high-temperature reactors (HTRs) has revealed a lack of experimental data for validating neutronics codes that are used for the design and licensing of such systems. In the framework of the ...
The deployment of a suitable, Pu-bearing inert matrix fuel (IMF) could offer an attractive option as a single-recycling LWR strategy aimed at reducing the currently growing plutonium stockpiles. A development programme focusing on yttria stabilized zirconi ...
The design of modern BWR assemblies is governed by general requirements such as safe and reliable performance, optimal fuel utilization and cycle length, and a high degree of flexibility in reactor operation. These requirements are fulfilled via the use of ...
One of the main goals of the FAST project at PSI is to establish a unique analytical code capability for the core and safety analysis of advanced critical (and sub-critical) fast-spectrum systems for a wide range of different coolants. Both static and tran ...
Phytoextraction is an environmentally sound method for cleaning up sites that are contaminated with toxic heavy metals. However, the method has been questioned because it produces a biomass-rich secondary waste containing the extracted metals. Therefore, f ...
The appropriate management of radioactive waste arising from the nuclear fuel cycle is considered to be a key issue in the development of future, more sustainable nuclear energy systems. In this context, the partitioning and transmutation of actinides coul ...
This paper considers the minimization of batch time for an industrial inverse-emulsion polymerization reactor in the presence of uncertainty. A first optimization study resulted in the current industrial practice of a semi-adiabatic profile (isothermal ope ...
Within the European Union, the two major breeding blanket concepts presently being developed are the helium cooled pebble bed (HCPB), and the helium cooled lithium lead (HCLL) blankets. For both concepts, different conceptual designs are being discussed wi ...
Boiling water reactor (BWR) stability analysis is usually carried out using large system codes. However, because of the large computational efforts required, such codes cannot in practice be employed for the detailed investigation of the complete manifold ...
