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Beryllium moderated reactors / Nuclear reactors / Graphite moderated reactors / Molten salt reactor / Energy conversion / Molten-Salt Reactor Experiment / FLiBe / Fusion power / DEMO / Nuclear technology / Nuclear physics / Energy


ASSESSMENT OF FIRST WALL AND BLANKET OPTIONS WITH THE USE OF LIQUID BREEDER C.P.C. Wong, S. Malang,1 M. Sawan,2 S. Smolentsev,3 S. Majumdar,4 B. Merrill,5 D.K. Sze,6 N. Morley,3 S. Sharafat,3 M. Dagher,3 P. Peterson,7 H.
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Document Date: 2006-01-18 17:05:28

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City

Madison / Linkenheim / Argonne / Zinkle / Los Angeles / San Diego / /

Company

Advanced Ferritic Steel / California 8Oak Ridge National Laboratory / 1Fusion Nuclear Technology Consulting / MSRE Systems / Sandia National Laboratory / California 4Argonne National Laboratory / ITER Test Blanket Module Working Group / Fusion Energy Systems / /

Continent

Europe / /

Country

Japan / United States / Korea / China / /

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Facility

Advanced Reactor Power Plant / Reactor Design / /

IndustryTerm

metal / Blanket energy multiplication values / possible design solutions / cycle systems / nuclear systems / reduced activation ferritic steel / steel structure / steel / /

NaturalFeature

FW stream / /

OperatingSystem

Microsoft Windows / /

Organization

U.S. Department of Energy / European Union / SC FLiNaBe / /

/

Position

Major / General / Engineer / /

ProgrammingLanguage

EC / DC / /

ProvinceOrState

Missouri / New Mexico / Wisconsin / New Brunswick / South Carolina / Illinois / Mississippi / California / Idaho / /

Technology

3-D / heat transfer / thermal insulation / /

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