3-D Monte Carlo analyses of the shielding system in a tokamak fusion reactor
In the frame of the ITER (International Tokamak Experimental Reactor) design program, 3D neutronics calculations were carried out to assess the system shielding performance in the basic machine configuration by means of the Monte Carlo Neutron Photon (MCNP) code (3-B version). The main issue concerns the estimate of the nuclear heat and radiation loads on the toroidal field superconducting coils. "Self generated weight windows" and the source biasing technique were used to treat the deep penetration through the bulk shield and the streaming through the system gaps and openings. The main results are reported, together with a discussion of the computing methods and the variance reduction techniques adopted.
Bibliographic Reference: Paper presented: International Conference on Monte Carlo Methods for Neutron and Photon Transport Calculations, Budapest (HU), Sept. 25-28, 1990
Availability: Available from (1) as Paper EN 35857 ORA
Record Number: 199110039 / Last updated on: 1994-12-02
Original language: en
Available languages: en