Physical and dosimetric studies in therapy of malignant tumors with BR-10 reactor fast neutron

Long-term experience was generalized on physical and dosimetric provision of the neutron-co-shock therapy of malignant tumors with the use of neutrons from B-3 channel of the BR-10 reactor. Suggested data show that the absorbed dose more than by 90 % is determined by the fast neutrons both in spectrum of incident beam and in spectrum inside a phantom. Thermal neutron contribution into the flux increases with the depth. Relative contribution into the flux and into kerma of intermediate neutrons (1-100 keV) doesn't increase. Determination of the absorbed dose under conditions of equilibrium absence is based on the computation methods (Monte-Carlo method)