[en] An attempt is made to generalize the experience gained in designing shields of thermonuclear devices using the DT reaction and tokamak reactors with magnetic plasma confinement, and to single out the most vital problems to solve. A peculiarity of the radiation source is underlined, which is close to a monoenergetic one with 14.06 MeV neutrons. The fact brings about substantial complications in calculations due to lack of group constant software. Specific features of calculations of neutron transport in the first wall and the blanket (''pure'' and ''hybride''), of the radiation heating and damage in the winding shields, special shields and biological shields are discussed. Among the most vital problems for investigations singled out are development of multidimensional computer codes to calculate neutron and gamma fields in the blanket and the first wall, development of the constants data banks and codes for optimization of the blanket and shields over different parameters