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However, most of that effort relied on manually passing information between models that describe different length and time scales. A more integrated approach 31 is being adopted in current research in the European Union. Three prominent areas requiring further model development and integration are described in the following sections. 1 Interatomic potentials for radiation damage There are a large number of published interatomic potentials designed for various purposes, whose suitability for use in radiation damage studies varies.

This is clearly a basic feasibility issue for use of LAMS in fusion structures. High concentrations of hydrogen may also be very damaging [9,10]. This form of embrittlement decreases at higher temperatures, but the use of LAMS may be limited by other properties such as possible swelling at around 400-450°C and thermal creep, structural instabilities, softening and non-hardening embrittlement at still higher temperatures [19,20]. Thus the temperature window for LAMS could be very limited. Another key issue is irradiation creep that operates over a very wide temperature range; and this phenomena will make fusion structures inherently dimensionally unstable even if high levels of helium and hydrogen do not trigger rapid void swelling.

6°C/MPa [17]. Since peak hardening is expected to be on the order of 500 to 600 MPa for irradiations at lower to intermediate temperatures, large ∆To of more that 300°C, corresponding to inservice To of 200°C or more are possible from displacement damage alone. However, recently spallation proton data has shown that bulk helium levels of 600-800 appm also severely weaken grain boundaries. Reduced local fracture stresses interact synergistically with large amounts of irradiation hardening, producing very brittle intergranular (IG) facture.

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Advanced Computational Mtls Science - Appl to Fission, Fusion Reactors

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