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

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

F.А. Garner, M.B. Toloczko, Bulent H. Sencer · Journal of Nuclear Materials · 2000 · 569 citations

Natural Sciences, Materials Engineering, Materials Science +13

Ferritic/martensitic steels – overview of recent results

R.L. Klueh, D.S. Gelles, S. Jitsukawa et al. · Journal of Nuclear Materials · 2002 · 324 citations · Full text

Engineering, Materials Engineering, Materials Science +14

Void-swelling in irons and ferritic steels

E.A. Little, D.A.V. Stow · Journal of Nuclear Materials · 1979 · 286 citations

Natural Sciences, Materials Engineering, Materials Science +12

Current status and future R&D for reduced-activation ferritic/martensitic steels

A. Hishinuma, A. Kohyama, R.L. Klueh et al. · Journal of Nuclear Materials · 1998 · 252 citations

Engineering, Materials Engineering, Materials Science +14

Progress and critical issues of reduced activation ferritic/martensitic steel development

B. van der Schaaf, D.S. Gelles, S. Jitsukawa et al. · Journal of Nuclear Materials · 2000 · 201 citations

Engineering, Materials Engineering, Materials Science +14