Safety assessment for deep geological disposal of high-level radioactive waste

Author(s):  
Peter N. Swift
Author(s):  
Pierre Van Iseghem ◽  
Jan Marivoet

This paper discusses the impact of the parameter values used for the transport of radionuclides from high-level radioactive waste to the far-field on the long-term safety of a proposed geological disposal in the Boom Clay formation in Belgium. The methodology of the Safety Assessment is explained, and the results of the Safety Assessment for vitrified high-level waste and spent fuel are presented. The radionuclides having the strongest impact on the dose-to-man for both HLW glass and spent fuel are 79Se, 129I, 126Sn, 36Cl, and 99Tc. Some of them are volatile during the vitrification process, other radionuclides are activation products, and for many of them there is no accurate information on their inventory in the waste form. The hypotheses in the selection of the main parameter values are further discussed, together with the status of the R&D on one of the main dose contributing radionuclides (79Se).


Author(s):  
Akira Kitamura ◽  
Reisuke Doi ◽  
Yasushi Yoshida

Japan Atomic Energy Agency (JAEA) established the thermodynamic database (JAEA-TDB) for performance assessment of geological disposal of high-level radioactive waste (HLW) and TRU waste. Twenty-five elements which were important for the performance assessment of geological disposal were selected for the database. JAEA-TDB enhanced reliability of evaluation and estimation of their solubility through selecting the latest and the most reliable thermodynamic data at present. We evaluated and estimated solubility of the 25 elements in the simulated porewaters established in the “Second Progress Report for Safety Assessment of Geological Disposal of HLW in Japan” using the JAEA-TDB and compared with those using the previous thermodynamic database (JNC-TDB). It was found that most of the evaluated and estimated solubility values were not changed drastically, but the solubility and speciation of dominant aqueous species for some elements using the JAEA-TDB were different from those using the JNC-TDB. We discussed about how to provide reliable solubility values for the performance assessment.


Author(s):  
P. Marjatta Palmu ◽  
Torsten L. Eng

Several European waste management organizations have started the work on creating a technology platform to accelerate the implementation of deep geological disposal of radioactive waste in Europe. There is an increasing consensus in the international community [1] about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste, and other long-lived radioactive wastes. At the same time, the European citizens [2] have a widespread wish for a solution for high-level radioactive waste disposal. A majority of the European countries with nuclear power have active waste management programmes, but the current status and the main challenges of those programmes vary. The most advanced waste management programmes in Europe (i.e. Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a joint awareness that cooperation on the scientific, technical, and social challenges related to geological disposal is needed, and the cooperation will be beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. Several decades of research, development and demonstration (RD&D) have been carried out in the field of geological disposal. International opportunities of cooperation and establishing a technology platform were explored in the European Commission co-funded projects like Net.Excel [3] and CARD [4]. According to the CARD project, the majority of the funding for RD&D in waste management comes from the implementing organizations. It is envisaged that a technology platform would enhance European cooperation in this area. The platform intends to constitute a tool for reducing overlapping work, to produce savings in total costs of research and implementation, and to make better use of existing competence and research infrastructures. After the final workshop of the CARD project in 2008, SKB (Sweden) and Posiva (Finland) were committed to lead the preparation work to set-up the Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP). Other implementers from France, Germany, Switzerland, Great Britain, Spain, and Belgium joined en suite. A Vision Document for the IGD-TP is about to be finalized after a wider consultation was carried out in July 2009. The final Vision Document and the platform are launched during November 2009. Simultaneously, the preparation of the Strategic Research Agenda for the technology platform’s joint work starts.


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