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Research Needs for Magnetic Fusion Energy Sciences - US Burning ...

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Power Extraction<br />

• significant advance in predictive capabilities in key areas including, <strong>for</strong> example: coupling<br />

of cad models with neutron and photon transport codes; developing 2-d and 3-d liquid<br />

metal magnetohydrodynamics (mhd) numerical methods and simulation tools coupled<br />

with heat transfer simulations capable of exploring very complex liquid metal blanket<br />

flow physics; dynamic models of tritium fuel cycle behavior (a key need to assess tritium<br />

self sufficiency); and melcoR safety analysis code <strong>for</strong> power extraction components.<br />

• conception and initial development of the dual coolant lead lithium (dcll) blanket<br />

concept, providing a potential pathway to high outlet temperature and high efficiency<br />

power conversion with current generation reduced activation materials. The dcll is a<br />

significant driver of current research and international collaborations on silicon carbide<br />

(sic) development and irradiation experiments, mhd experiments and simulations of<br />

flow control and heat transfer, and tritium behavior in lead lithium alloys.<br />

• models and experimental validation of tritium release from and thermal conductivity of<br />

glass-like ceramic breeder particle beds.<br />

• First in-depth joint technology and physics investigation of the behavior of innovative<br />

liquid surface wall and divertor concepts. These were done as part of research programs,<br />

alPs and aPeX, that led to a much deeper understanding of issues and designs, as well<br />

as continuing experiments with lithium surfaces in confinement devices in the Us and<br />

abroad.<br />

• development of conceptual designs of attractive magnetic fusion energy power plants,<br />

including advanced divertor and blanket concepts <strong>for</strong> high-efficiency power generation<br />

(helping identify key R&d).<br />

• initial designs and analysis of iteR test blanket module experiments <strong>for</strong> both the lead<br />

lithium and ceramic breeder blanket systems to fully utilize the first long pulse fusion<br />

environment <strong>for</strong> investigating power extraction component behavior and phenomena.<br />

Materials Science<br />

• advances in the development of reduced-activation ferritic-martensitic steels with good<br />

thermal conductivity and thermal stress parameter, resistance to swelling at high dose,<br />

and with well-developed manufacturing technology <strong>for</strong> nuclear applications.<br />

• addressing key scientific questions concerning nanocomposited ferritic alloys. These<br />

alloys possess excellent high-temperature strength and show significant promise <strong>for</strong><br />

mitigating the damaging effects of neutron irradiation, including the potential to tolerate<br />

high levels of transmutation-produced gases such as helium and hydrogen.<br />

• exploring the application of rein<strong>for</strong>ced silicon carbide materials. While only a relatively<br />

small fraction of the fusion materials science research portfolio, the ef<strong>for</strong>t on fiber<br />

rein<strong>for</strong>ced silicon carbide composites has demonstrated tremendous potential. These<br />

truly low-activation materials have both structural and functional applications in fusion<br />

power systems.<br />

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