Decommissioning in Slovenia

Transcription

1 Decommissioning in Slovenia Gašper Tavčar

2 Slovenian nuclear programme 1. Krško Nuclear Power Plant 2. Research reactor TRIGA Mark II 3. Central Interim Storage Facility 4. Žirovski vrh uranium mine (Jazbec and Boršt repositories)

3 Nuclear power plant Krško Krško NPP with extended lifetime will operate until 2043 Decommissioning programme is prepared and should be revised every 5 years. The last revision was prepared in The Krško NPP operates under joint ownership of Slovenia and Croatia and all obligations (waste, decommissioning ) comming from this joint ownership are responsibility of both owners. The majority of Slovenian part of the operational and decommissioning waste will be disposed of in a LILW repository (the site which is near the NPP was selected last year). Fund for decommissioning of Krško NPP is established and it is financed through the levy per kwh which amounts to 0.3 Euro cents.

4 TRIGA Mark II research reactor Licensed in 1966 and re-licensed for steady state and pulse operation after renovation and reconstruction in 1991, Used in research projects, education and source production. It is operated by the Jožef Stefan Institute, a public research institution that is financed through the national budget by the Ministry for Higher Education, Science and Technology.

5 Strategy on operation and decommissioning According to The Resolution on the National Programme for Managing Radioactive Waste and Spent Nuclear Fuel the strategy about operation and decommissioning is following: Reactor will operate till 2016, spent fuel shipped back to USA, decommissioned after The spent fuel will be returned to the country of origin and while "US originating fuel repatriation program" was prolonged till 2019 the decision about the period of reactor operation was made in 2007 and the decommissioning plan was prepared at the same time. All LILW will be deposited in LILW repository, Decommissioning will be financed by the Ministry for Higher Education, Science and Technology

6 TRIGA Mark II research reactor 219 spent fuel elements were shipped within the scope of the US originating fuel repatriation program to the USA in July There are no spent fuel elements at the reactor now. 10 fresh fuel elements were transferred to France in 2007.

7 Žirovski vrh uranium mine Start of exploitation in 1982 Production of uranium concentrate started in 1984 Decision to close it in 1990 Remidiated Jazbec mine waste pile Boršt mill tailings site

8 Decontamination of buildings involved in past research on uranium extraction for nuclear technology Jožef Stefan Institute Treatment of liquid waste Different streams of liquid radioactive waste was treated by chemical processes to obtain solid radioactive waste and liquid waste. Nochar treatment Precipitation Liquid radioactive waste Coprecipitation

9 Decontamination of buildings involved in past research on uranium extraction for nuclear technology Jožef Stefan Institute Final treatment of waste Waste obtained from treatment and contaminated material was separated according to properties and further processed as necessary. Filtration Compressing Clearance measurement of liquid waste

10 Decontamination of buildings involved in past research on uranium extraction for nuclear technology Jožef Stefan Institute Technological hall was radiologically surveyed, emptied and decontaminated by different mechanical and chemical methods. Technological hall Contaminated areas

11 Decontamination of buildings involved in past research on uranium extraction for nuclear technology Jožef Stefan Institute Containers and tanks where solutions containing uranium were stored. The containers and tanks were chemically decontaminated as much as possible.deeply contaminated areas were cut out. A layer of soil under the containers was also removed. Sludge tank Decontaminated container Removal of the soil

12 Decontamination of buildings involved in past research on uranium extraction for nuclear technology Jožef Stefan Institute Radiological measurement Surfaces were checked through contamination measurements and in situ gamma spectroscopy. On sites with the highest probability of leak core samples were also taken. In situ gamma spectroscopy Contamination measurement Core sampling Final characterisation of packages