Abstract
The long-term radiological impact of underground disposal of vitrified HL W (high-level waste) resulting from different P&T strategies has been evaluated. The considered P&T strategies include recycling of Pu and Np in homogeneous mode and Am in heterogeneous mode in CAPRA reactors or EFRs (European Fast Reactor). The safety assessment has been performed for three different types of host rocks, i.e. hard rock, salt and clay. For comparison assessments have also been made for the direct disposal of irradiated classical PWR UOX and UOX and MOX fuel, and of CAPRA and of EFR fuels. The key radionuclides have been identified and the capabilities for their partitioning and transmutation have been assessed.
Original language | English |
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Title of host publication | Proceedings of the 5th international information exchange meeting on actinide and fission product partioning and transmutation |
Publisher | OECD NEA - Nuclear Energy Agency |
Chapter | Session VI |
Pages | 461-471 |
Number of pages | 10 |
State | Published - 25 Nov 1998 |
Event | 2018 - 5th international information exchange meeting on actinide and fission product partitioning and transmutation - Mol Duration: 25 Nov 1998 → 27 Nov 1998 |
Conference
Conference | 2018 - 5th international information exchange meeting on actinide and fission product partitioning and transmutation |
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Country/Territory | Belgium |
City | Mol |
Period | 1998-11-25 → 1998-11-27 |