BEHAVIOUR OF BERYLLIUM IN A TOKAMAK FUSION REACTOR
The behaviour of beryllium in a fusion plasma was studied by using the BITC (Bologna Impurity Transport Code) code for the parameters of the JET. The radial profiles of Z-effective, ionization states and fluxes are given. The radiation losses by the beryllium impurity in a fusion reactor are estimated less than 1% of the total power input. The radiation losses by beryllium in corona equilibirum are also presented.
Bibliographic Reference: WRITE TO MAX-PLANCK-INSTITUT FUER PLASMAPHYSIK, 8046 GARCHING BEI MUENCHEN (GERMANY), MENTIONING REPORT IPP 6/228, 1983
Record Number: 1989122018700 / Last updated on: 1987-01-01
Available languages: en