Annals of Nuclear Energy - Volume 34 - Issue 6 

Absolute measurement of βeff based on Feynman-α experiments and the two-region model in the IPEN/MB-01 research reactor

Fulltext Access 10 Pages 2007

Neutron transport benchmark problem proposal for fast critical assembly without homogenizations

Fulltext Access 6 Pages 2007

DYN3D-MSR spatial dynamics code for molten salt reactors

Fulltext Access 14 Pages 2007

Reactor noise in accelerator driven systems – II

Fulltext Access 20 Pages 2007

Simulating the dynamics of the neutron flux in a nuclear reactor by locally recurrent neural networks

Fulltext Access 13 Pages 2007

Estimation of the amount of surface contamination of a water cooled nuclear reactor by cooling water analysis

Fulltext Access 5 Pages 2007

Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis

Fulltext Access 13 Pages 2007

Calculation of neutron importance function in fissionable assemblies using Monte Carlo method

Fulltext Access 7 Pages 2007

Approximate solutions of point kinetics equations with one delayed neutron group and temperature feedback during delayed supercritical process

Fulltext Access 6 Pages 2007

Least-squares finite-element SN method for solving three-dimensional transport equation

Fulltext Access 6 Pages 2007