ITER Task T 426 EU SHUT DOWN DOSE

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ITER Task T 426 – EU SHUT DOWN DOSE RATE EXP. for ITER Objective

ITER Task T 426 – EU SHUT DOWN DOSE RATE EXP. for ITER Objective : verify shut down dose rate calculation for ITER outvessel, in-cryostat for tcool 1 month Mock-up irradiated at FNG (3 days) to have a detectable dose rate (ENEA, TUD, FZK) The shut down dose rate outside the ITER vessel is calculated by 2 -step method (MCNP/FISPACT) and by 1 -step method (MCNP-modified), using and FENDL-2 data, within 15% from a few days up to 2 months of decay time

EU Fusion Technology Program – Nuclear Data Experimental validation of EAF activation cross sections

EU Fusion Technology Program – Nuclear Data Experimental validation of EAF activation cross sections 1. 5 üDetecting system developed to measure • Beta power EUROFER long irradiation time C/E Gamma power • Gamma power simultaneously the total activity of a neutron irradiated material and the electron and photon decay heats 0. 5 üActivation/decay heat in EUROFER C/E 1. 0 EUROFER 0. 0 1 10 100 Decay time (hours) 1000 g- and b-decay heat measured up to tcool ~ 20 days, g- activity measured up to several months of cooling time Deficencies in beta decay heat identified in the comparison with EAF predictions üDecay heat in 12 materials (Cu, Ag, Sn, Cd, Mg, Hf, Mo, Al, Ti, Ni, W, Re) g- and b-decay heat measured and compared with EAF predictions Some deficencies identified in EAF üActivation/decay heat in Cr and other materials is in progress (2001 activity)

EU Fusion Technology Program – Nuclear Data Validation of EFF cross sections for advanced

EU Fusion Technology Program – Nuclear Data Validation of EFF cross sections for advanced materials. Si. C EXPERIMENT at FNG (2000 -2001) (ENEA, TUD, FZK, IJS) Objective Provide validation of EFF data for Silicon carbide which is a candidate low activation material for the fusion reactor, and is considered for development in the European Fusion Technology Program (Si. C block on loan from JAERI within IEA collaboration)

EU Fusion Technology Program – Nuclear Data Validation of EFF cross sections – Si.

EU Fusion Technology Program – Nuclear Data Validation of EFF cross sections – Si. C experiment Measurements (already completed) • neutron and gamma spectra (TUD) • Activation (ENEA) • nuclear heating (ENEA) Analysis (in progress) • C/E for all measured quantities for EFF (and FENDL-2) libraries • Sensitivity /uncertainty analysis based on 3 D MC and 2 D deterministic approaches