Abstract: A method for calculating loads deposited by an ionizing radiation, for example to be used by a radiotherapy therapeutic treatment device. The method includes at least one first step of calculating a function of the distribution of the load in the meshes of a mesh phantom. The method includes a second step of calculating the load deposited in a voxel assembly, the value of the deposited load for one voxel being given by the function of the distribution of the load particular to the mesh to which the voxel belongs. The invention can be used in particular for radiotherapy by intensity modulation.

Abstract: The present invention relates to a polymer composition equivalent to the biological tissue and having a very high resistivity. The invention also relates to the use of this composition in the production of the cathode (3") of a proportional counter equivalent to the biological tissue, as well as to a counter incorporating such a cathode.This composition is characterized in that it is formed from a polyamide, polypropylene, epolene and carbon black and in that it has a mass atomic composition such that the hydrogen is between approximately 6 and 14%, the carbon between approximately 55.5 and 86.5%, the nitrogen between approximately 2.5 and 4.5%, the oxygen between approximately 1.5 and 7.5%, the calcium between approximately 1.5 and 9.5% and the fluorine between approximately 1 and 9%, the sum of the carbon, oxygen and fluorine quantities in the total composition being between approximately 72 and 90%.

Abstract: A radiation dose rate meter is provided which includes a diode for sensing radiation, and an electric measuring circuit divided into two branches having different frequential filters, one filter for measuring alpha particles, protons and neutrons and another filter for measuring electrons and photons (i.e., particles that deliver differently shaped pulses of upon reaching the diode). The dose rate meter is able to accurately determine the dosage of radiation effectively received.

Abstract: Individual measuring device for the neutron dose equivalent comprising a detector (10) constituted by two identical diodes (13, 14). The first diode (13) is covered by a charged particle neutron converter (16). Converter (16) and the second diode (14) are covered by a protective screen (12). A differential measurement is performed between the signals from the two diodes (13, 14), which makes it possible to eliminate spurious noise. The result of the subtraction is multiplied by a given coefficient to obtain the neutron dose equivalent.Application to radiation protection.