EURAC: The JRC proposal for a European fusion reactor materialse vst and development facility: Commission of the European Communities

Abstract

The United States Department of Energy has spent in the last 10 years more than 100 Mill US$ for the development of intense neutron sources for a fusion reactor material test and development programme based on the D +−T and D +−Li stripping reactions. The final design parameters for the large Fusion Materials Irradiation Test (FMIT) facility are: • - Linear Accelerator: 35 MeV, 100 mA-deuteron-beam on a liquid lithium target. • - Irradiation parameters: 83 dpa/year in 10 cm 3 11 He appm/dpa. For the last 6 years we examined the use of a Spallation Neutron Source (SNS) as an alternative European Option to FMIT. For an optimized spallation neutron source design we find now for the same beam power as FMIT the following design parameters: • - Linear Accelerator: 600 MeV, 6 m-A-proton beam on liquid lead target. • - Irradiation parameters: 320 dpa/year in 20 cm 3 or 274 dpa/year in 31.5 cm 3 6 < He appm/dpa ⩽ 13. For a Tokamak Experimental Power Reactor such as INTOR (1.3 MW/m 2 wall loading) the design parameters are: 15 dpa/year and 11 He appm/dpa. If we compare FMIT with an optimized spallation neutron source of equal beam-power or neutron production cost, we arrive at the following figure of merit: p ]The present conceptual spallation neutron source target would allow us to use a 1200 MeV, 24 mA-proton beam, if required. The Ispra SNS-Target Station will be designed for these parameters. For synergetic experiments concerning fatigue and radiation damage the continuous proton beam will be periodically deflected on the target: Δt = 9s, f = 10 −1 s −, in order to simulate the Pulsed Mode of Tokamak Power Reactors. The deflected beam can be used for other experiments.