Computational-Experimental Study of the Heating of Structural Materials by IGRIK Radiation

An experiment measuring the temperature to which small samples of W, Ta, Mo, Cu, Zr, Ni, Fe, Ti, Sn, and Pb are heated by IGRIK radiation is performed. The technology for placing the thermocouples is described, the results of an analysis of the elemental composition of the samples are presented, and the experimental results from measurements of the heating temperature are also presented. The PRIZMA.D and MCNP computer codes are used to calculate the neutron and γ-ray energy losses in samples irradiated by a reactor pulse. The heat-up temperature is calculated. Discrepancies in calculations performed of the neutron and γ-ray energy losses in samples of the materials using different nuclear data libraries are shown. It is shown that the heating temperature calculated on the basis of the calculation of the neutron and γ-ray energy losses in the material of the samples, using the PRIZMA.D program with the BAS nuclear data library, agrees with the experimental value to within 5%. The agreement obtained with the MCNP code using the ENDF-B5 and -B6 libraries is no worse than 10-15%.[PUBLICATION ABSTRACT]