Georgia (based on JC national report): National framework for management of spent fuel and radioactive waste

The country does not have any nuclear enterprise. Only one nuclear research reactor was operated during 1959-1989 years. The reactor belongs to the Applied Research Center of E. Andronikashvili Institute of Physics (IP). After the shut down the reactor all spent and fresh fuel was removed from the Georgia. The reactor decommissioning was started within IAEA TC projects. As a first step entombing of the reactor core was conducted. The decommission activity is still going aiming dismantling of the reactor auxiliary systems. (IP was joined to Tbilisi State University at 2011). IP also operated subcritical assembly, which was dismantled at 2015 and 36% enriched 1280g Uranium contained in the assembly was repatriated to the country of origin. The operation was conducted within RRRFR programme and supported by IAEA and US. At the site of Applied Research Center Centralized Storage Facility was constructed and put into operation. As results there are only appr. 4 kg nuclear material kept at CSF, which was detained during illegal activities. CSF was operated by IP until the beginning of 2016. Georgia had one historical closed disposal site- s.c. Saakadze disposal. The disposal is typical Radon type disposal containing mainly VLLW and LLW. The country strategy for radioactive waste management is under process of elaboration based on Swedish support and should be adopted at the end of 2016. To increase the effectiveness of using of limited resources for ensuring safety of radioactive waste management Government of Georgia implemented new reform – Both facilities was transferred for operation to Department of Radioactive Waste, which was established at Agency of Nuclear and Radiation Safety The radioactive waste management actions should follow the openness and stakeholder involvement principles. Final disposal is regarded as the ultimate step in the radioactive waste management process although a step-wise waste management approach is acceptable. Long-term storage of certain types of wastes (e.g. VLLW, LLW and spent sources) may be regarded as one of the steps in the management process. The aim shall be to achieve a maximum degree of passive safety in storage facility and disposal. The design, construction, commissioning, operation, decommissioning and closure of waste generating and disposal facilities shall be in accordance with all applicable regulatory requirements. The following hierarchy of waste management options shall be followed where practicable: • Avoidance and minimization of waste trough: • Re-use, reprocessing and recycling; • Storage; • Conditioning and disposal. To minimize the burden on future generations, decommissioning and closure of facilities should be implemented as soon as practicable. The deliberate dilution of radioactive waste is not acceptable, however in the case of NORM waste the dilution of higher concentration material with lower concentration material will be considered provided all relevant regulatory concerns are addressed. All safety requirements are implemented through radiation protection programmes of licensee handling with radioactive waste. Especial attention is paid to minimizing of waste generation, its segregation, avoidance of hazards and limitation for discharge to environment.