9 records found
1
Generation of multi-group cross sections and scattering matrices with the Monte Carlo code MCNP5
Reactor physics aspects of low void fuel-phase 2, Final report, Contract No: 87055-04-0269, Rapport PNR-131-2005-001, March 2005
Benchmark calculations of power distribution within assemblies. Phase II: comparison of data reduction and power reconstruction methods in production codes, Issy-les-Moulineaux, France, 2000
On-site spent fuel management based on electrorefining
Conceivable limits for the thermal reactor spent-fuel recyling
Statics and dynamics of a fluidized bed fission reactor
On-site spent fuel management
Studies on the inhomogeneous core density of a fluidized bed nuclear reactor
