REMOVAL OF RESEARCH REACTOR SPENT FUEL FROM DALAT NUCLEAR RESEARCH INSTITUTE TO RUSSIA FOR REPROCESSING

In 1963, the U.S. General Atomics constructed the TRIGA Mark II research reactor in Dalat Nuclear Research Institute. In 1983, the reactor was reconstructed to the Soviet Union design named IVV-9 reactor. It has been successfully used for production of radioisotopes, neutron activation analysis, personnel training and other research purposes. In 2007, under the Russian Research Reactor Fuel Return (RRRFR) Program, non-irradiated highly enriched uranium (HEU) VVR-M2 fuel assemblies were removed and low enriched uranium (LEU) VVR-M2 assemblies were supplied to DNRI for conversion of the reactor. In 2011, the HEU spent fuel assemblies (SFAs) were reloaded from the reactor core into the spent fuel storage pool and the reactor was fully converted to VVR-M2 LEU fuel. The paper analyzes the work done for the transportation of the spent fuel in the TUK-145/C package based on the SKODA VPVR/M cask, describes the main documents and equipment developed for loading the SFAs into the cask. The safety of the operations was supported by the analysis of the equipment design and nuclear and radiation safety. The paper describes the DNRI personnel training in operation of the equipment fabricated for loading the SFAs into the SKODA VPVR/M cask and a new procedure for reloading the SFAs (“dry” top loading of the SFAs into the SKODA cask with a transfer cask).