The cross sections for radiative capture and fission for 236 U in the neutron energy ranges 1-2000 eV and 1-1000 eV, respectively, have been measured. The measurements were performed on a flight baseline 5.2 m of the FAKEL linear electron accelerator at the National Research Center Kurchatov Institute using a method based on measuring the distribution of the number of particles emitted by an excited nucleus with simultaneous measurement of the energy of each particle. The spectrum of the neutrons incident on a sample was measured by detecting the reaction 10 B(n, α) 7 Li. The cross sections were normalized with respect to the resonance in 236 U at 5.45 eV. The data obtained are compared with the results of other experiments and evaluated data.The neutron radiative capture cross section for 236 U is of considerable interest for calculating nuclear reactors, since it accumulates in the fuel and absorbs a large fraction of the neutrons with very little subsequent fission. In addition, it is necessary to know this cross section to develop a technology for reprocessing radioactive wastes.Most experimental data on the radiative capture cross section were obtained for neutron energies greater than several kilo-electron-volts. Below E n~ 2 keV the capture cross section has been measured directly in two experiments [1, 2], whose results are clearly at variance. In [2], the cross section was determined only above 300 eV. In the region where the energy ranges overlap, the data of [1] are approximately 20% higher than in [2]. At the same time, the required error in this quantity is 5% in the indicated region.The procedure examined in the present article makes it possible to obtain, in addition to the capture cross section, information about the fission cross section, which can serves as a basis for developing a new independent method of measuring small fission cross sections. Measurement Procedure. The capture cross section was obtained, as in [1], by means of a universal method based on measuring the distribution of the number of particles emitted by an excited nucleus and simultaneously determining the energy of each particle [3]. The essence of the method is to identify, by measuring the distribution of the number of γ-rays emitted as a result of an interaction, events with different types of neutron-nuclei interactions. The distribution is the dependence of the number of events on the number of emitted γ-rays. Radiative capture, fission, and scattering events are concentrated in different regions of this distribution, and this is what makes their separation possible. The indicated distribution is measured using a multi-section scintillation 4π-detector with almost 100% efficiency by recording multiple coincidences of counts from its sections. The experimental sample is placed at the center of a through channel of the detector, through which the neutron beam passes. To protect the scintillator from the neutrons scattered by the sample, the channel is surrounded by a layer of 10 B, which serves simultaneously as a (n, γ) c...