23 records found
1
Fuel cycle investigation for wallpaper-type HTR fuel
Performance of TRISO particles fuelled with plutonium and minor actinides in a PBMR-400 core design
Optimization of a radially cooled pebble bed reactor
Validation of the DALTON-THERMIX code system with transient analysis of the HTR-10 and application to the PBMR
In-core fuel management optimization of pebble-bed reactors
Optimized core design and fuel management of a Pebble-Bed type nuclear reactor
Evaluation of experiments in the AVR with the DALTON-THERMIX coupled code system
Bestuurslid Dutch Young Generation
Stress analysis of coated particle fuel in graphite of High Temperature Reactors
Coupled neutronics/thermal-hydraulics calculations for High Temperature Reactors with the Dalton-Thermix code system
RAPHAEL core physics: neutron and thermal-hydraulic simulation of the HTR-10 and AVR reactors. Contribution for RAPHAEL core physics, PNR-131-2008-012, Ocrtober 2008
None
Assesment of VHTR core design with regard to fuel temperature: Normal operation. Deliverable (D-SI2.1) RAPHAEL System Integration, July 2008
Development of a stress analysis code for TRISO particles in HTRs
Assesment of VHTR core design with regard to fuel temperature; Loss of forced cooling conditions. Deliverable (D-SI2.2) RAPHAEL System Integration, PNR-131-2008-011, October 2008
Static design of a Liquid Salt-cooled Pebble Bed Reactor (LSPBR)
Mechanical stresses in fuel particles and graphite in high temperature reactors
Neutronic Design of a Liquid Salt-cooled Pebble Bed Reactor (LSPBR)
