The preparations of the MP research loop reactor for decommissioning are described. After final shutdown in 1993, a system of measures to ensure the required level of nuclear and radiation safety for the complex was implemented and a concept and fundamental program for decommissioning the reactor were developed. The variant DECON was taken as the base variant for decommissioning -immediate staged disassembly of structures and equipment, including disassembly of in-vessel structures of the RFT predecessor reactor which are stored in a central room of the reactor. The main results of the work performed to normalize the radiation conditions in the central room and to examine the safety-and-control system repository in this room are presented.The experimental reactor base at the Russian Science Center Kurchatov Institute consisted of 12 research facilities with different types of reactors, 19 critical benches, and other radiation-hazardous objects, including "hot" laboratories, irradiation facilities, and temporary repositories for spent nuclear fuel and radioactive wastes. Six of these reactor facilities continue to operate. The other six had been shut down for decommissioning and have been partially or completely disassembled ( Table 1). The greatest work to be done in decommissioning the reactors at the Kurchatov Institute which have been shut down is for the multipurpose, materials research, MR loop reactor [1].Characteristic Features of the Structure and Arrangement of the Reactor. The reactor was developed and built in 1962-1963 and reached the nominal power level 20 MW in 1964. Structurally, this was the first research reactor of a new type -a channel reactor immersed in a pool with water (Fig. 1). The 1 m high core together with the working and experimental channels, pipelines for dispensing the coolant, collectors, and other metal structures are placed in a distillate-filled pool more than 9 m deep and surrounded by concrete radiation shielding.The reactor is equipped with nine loop facilities for conducting tests and investigations of the fuel elements, the fuel, and the structural materials. These loop facilities make it possible to determine the thermophysical, hydrodynamic, and strength characteristics of the core and main equipment of power reactor facilities, designed for different purposes, under conditions approximating the actual working conditions as closely as possible (Table 2). In 1967, after reconstruction, the power of the reactor together with the circuit facilities was increased to 50 MW.