Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins

Swelling behavior of U-Pu-Zr fuel

G.L. Hofman, R. Pahl, C.E. Lahm et al. · Metallurgical Transactions A · 1990 · 148 citations

Engineering, Materials Engineering, Materials Science +9

History of fast reactor fuel development

Jean Kittel, B.R.T. Frost, J.P. Mustelier et al. · Journal of Nuclear Materials · 1993 · 141 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +11

Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors

L.C. Walters, B. R. Seidel, Jean Kittel · Nuclear Technology · 1984 · 122 citations

Engineering, Nuclear Engineering, Metallic Materials +16

Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C

Bulent H. Sencer, Jacob Kennedy, James I. Cole et al. · Journal of Nuclear Materials · 2009 · 86 citations

Engineering, Materials Engineering, Materials Science +12

Metal fuel test program in the FFTF

A.L. Pitner, R.B. Baker · Journal of Nuclear Materials · 1993 · 61 citations

Engineering, Materials Engineering, Materials Science +11