The activity dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport. Applications encompassed transport through large and complex shields including void regions and highly heterogeneous reactor cores. Methods included discrete ordinates, nodal transport, finite elements with spherical harmonics, collision probabilities, Monte Carlo, etc.
The objectives were to:
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neutron kinetics equations without use of the diffusion approximation and spatial homogenisation.
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) will perform specific tasks associated with reactor physics aspects of present and future nuclear power systems.
The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) deals with the various aspects of the modelling and design of accelerator shield systems and radiation facilities.