Measurement of the temperature of structural materials heated by radiation from a pulsed uranium-graphite reactor

The temperature of radiation heating by radiation from a pulsed uranium graphite reactor of small samples of tungsten, tantalum, molybdenum, chromium, copper, zirconium, nickel, iron, graphite, titanium, the aluminum alloy AMg-6, tin, lead, polyethylene, and free thermocouples is measured experimentally. The measurement apparatus and the technology for installing the thermocouples are described, and it is demonstrated that the tail of the burst and the delayed γ radiation affect the heating of the samples, and the energy loss during natural cooling of a sample is estimated. It is shown that the heating temperature of certain materials in a reactor run with maximum energy release reaches hundreds of degrees, and this must be taken into account when setting up an experiment and analyzing the results. 4 figures, 1 table, 6 references.