Engineering Codes' Numerical Benchmarks for RBMK-1000 Nuclear Reactor

Solutions to a number of neutron transport problems, typical for RBMK-1000 reactor calculations were developed with the MCU-REA code, based on a Monte-Carlo method approximately 400 relatively simple problem variants - infinite height cylindrical and square cells and some poly-cells were considered. At that stage sole simplification of the complex internal structure of the RBMK cells was the homogenization of the fuel rods spacers. The burnup calculations were carried out with the detailed account of circa 50 isotopes history. The obtained results are supposed to be used as numerical benchmarks for the verification of engineering code complexes and their separate modules for RBMK-1000 calculations. They can also be considered as results of numerical experiments and analyzed to achieve better understanding of complex fine features of neutron physics processes in reactor. (authors)