5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P1.200 Radiological impact mitigation of waste coming from the European Fusion Reactor DCLL DEMO

5 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 200
Poster J. Power Plants Safety and Environment, Socio-Economics and Technology Transfer P1 Poster session

Speaker

Raquel Garcia (Power Engineering Department)

Description

In large fusion machines, as the foreseen DEMO, the high energy neutrons produced will cause the transmutation of the interacting materials which become a source of radioactive waste. One of the main presuppositions for the global interest in nuclear fusion is that it should be cleaner and safer comparing with traditional nuclear technology. This implies, among other considerations, that the radioactive waste produced in a fusion power plant is expected to be categorized as “low level waste” after no more than 100 year since the shutdown. Besides the main constituents of a material that could transmutate but which presence is essential, the impurities, either naturally occurring or originated from the manufacturing process, often give rise to significant additional activation compared to the base material. Thus, once identified the elements generating the dominant activation products in each material of the DCLL (Dual Coolant Lithium-Lead) design option for the European DEMO, the objective of the study has been to determine the impurity limits for such materials in order to minimize the radiological impact of the waste produced and taking into account the industrial viability of the impurity reduction. For both the original compositions and the revised ones (i.e. compositions with reduced amount of impurities suggested to mitigate the waste impact) activation calculations have been performed. Hence, total beta-gamma activity, alfa activity, specific activity for different nuclides, decay heat and surface gamma dose rate have been analysed with reference to the IAEA standards for waste classification and to the specific regulations of the Spanish facility “El Cabril” for waste disposal. The analyses have entailed the use of the transport Monte Carlo code MCNP5, the inventory code ACAB, and the nuclear data libraries JEFF3.1.1 and EAF2007 for transport and activation respectively.

Co-authors

Iole Palermo (Fusion Technology Division, Ciemat, Avda. Complutense 40, 28040 Madrid, Spain) Javier Sanz (Power Engineering Department, Uned, Juan del Rosal, 12 28040 Madrid, Spain) Mauricio Garcia (Power Engineering Department, Uned, Juan del Rosal, 12 28040 Madrid, Spain) Raquel Garcia (Power Engineering Department, Uned, Juan del Rosal, 12 28040 Madrid, Spain)

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