New concept of designing Pu and MA containing fuel for fast reactors

Fuels for sodium-cooled fast reactors: US perspective

Douglas C. Crawford, S.L. Hayes · Journal of Nuclear Materials · 2007 · 307 citations

Engineering, Mechanical Engineering, Nuclear Engineering +12

Dispersion type zirconium matrix fuels fabricated by capillary impregnation method

I. I. Konovalov, A. V. Vatulin, V. K. Orlov et al. · Journal of Nuclear Materials · 2007 · 30 citations

Natural Sciences, Materials Engineering, Materials Science +8

Inert matrix fuel with low melting point zirconium brazing alloys

A. V. Vatulin, I. Dobrikova, S. A. Ershov et al. · Journal of Nuclear Materials · 2006 · 16 citations

Natural Sciences, Materials Engineering, Materials Science +14